european organization for nuclear research · introduction 2. irradiation conditions 3....

255
I CERN 82-10 Health and Safety Department 4 November 1982 ORGANISATION POUR LA RECHERCHE NUCLi;AIRE CERN EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH COMPILATION OF RADIATION DAMAGE TEST DATA PART III: Materials used around high-energy accelerators INDEX DES RESULTATS D'ESSAIS DE RADIORESISTANCE Ille PARTIE: Materiaux utilises autour ' des accelerateurs de haute energie P. Beynel, P. Maier and H. Schanbacher GENEVA 1982

Upload: others

Post on 19-Oct-2020

0 views

Category:

Documents


0 download

TRANSCRIPT

Page 1: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I

CERN 82-10 Health and Safety Department 4 November 1982

ORGANISATION EUROP~ENNE POUR LA RECHERCHE NUCLi;AIRE

CERN EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH

COMPILATION OF RADIATION DAMAGE TEST DATA

PART III: Materials used around high-energy accelerators

INDEX DES RESULTATS D'ESSAIS DE RADIORESISTANCE

Ille PAR TIE: Materiaux utilises au tour '

des accelerateurs de haute energie

P. Beynel, P. Maier and H. Schanbacher

GENEVA 1982

Page 2: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

CERN-Serviced'information scientifique -RDi564 - 2500 novembre 1982

Page 3: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

ABSTRACT

This handbook gives the results of radiation damage tests on various engineering materials and components intended for installation in radiation areas of the CERN high-energy particle accelerators. It complements two previous volumes covering organic cable-insulating ma­terials and thermoplastic and thermosetting resins.

The irradiations have been carried out at various ra­diation sources and the results of the different tests are reported, sometimes illustrated by tables and graphs to show the variation of the measured property with ab­sorbed radiation dose. For each entry, an appreciation of the radiation resistance is given, based on measure­ment data, indicating the range of damage (moderate to severe) for doses from 10 to JO' Gy.

Also included are tables, selected from published re­ports, of general relative radiation effects for several groups of materials, to which there are systematic cross-references in the alphabetical part. This third and last volume contains cross-references to all the mate­rials presented up to now, so that it can be used as a guide to the three volumes.

RESUME

Ce manuel donne Jes resultats d'essais sur la resis­tance aux rayonnements ionisants de materiaux et de divers composants d'equipements susceptibles d'etre installes dans des zones actives des accelerateurs de particules a haute energie du CERN. 11 est le comple­ment de deux volumes deja parus qui couvrent, l'un les materiaux organiques pour !'isolation de cables, l'autre les resines thermoplastiques et thermodurcissables.

Les irradiations ont ete effectuees aupres de diverses sources de radiations, et les resultats des differents tests sont rapportes, parfois illustres de tableaux et gra­phiques pour montrer la variation de la propriete mesu­ree avec la dose absorbee. Pour chaque ob jet, on donne une estimation de la radioresistance, basee sur des me­sures, offrant une echelle de dommagcs (moderes a severes) pour des doses allant de 10 a JO' Gy.

Sont inclus egalement des tableaux montrant !es effets generaux de !'irradiation pour plusieurs groupes de materiaux selectionnes de rapports publies; dans la partie alphabetique des renvois aces tableaux son! faits systematiquement. Ce troisierne et dernier volume com­prend des renvois a tous Jes materiaux testes jusqu'a present, ce qui en fait un guide pour !es trois volumes.

111

Page 4: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

CONTENTS

!. Introduction

2. Irradiation conditions

3. Presentation ofresults

4. General comparative results of radiation effects

5. Classification of materials

Acknowledgements

References

Page

2

4

5

5

7

8

Les chapitres 1 a 5, et l'appendice 7, sont traduits en franrais

Appendix l: Names, in alphabetical order, of all materials for which test results are presented in these volumes 14

Appendix 2: Explanation of trade names and popular names 16

Appendix 3: List of firms who collaborated in the irradiation tests presented in this volume 17

Appendix 4: List of abbreviations used in this volume 18

Appendix 5: Tables of general relative radiation effects 19

Appendix 6: Classification of materials and components contained in this volume according to the dose range up to which they may typically be used

Appendix 7: Detailed description of data entry sheets

Alphabetic compilation of data

31

32

35

TABLE DES MATIERES

I. Introduction

2. Conditions d'irradiation

3. Presentation des resultats

4. Resultats generaux comparatifs des effets de !'irradiation

5. Classification des materiaux

Remerciements

References

Appendice 7: Description detaillee des feuilles de donnees

Page

3

4

5

6

7

8

32

v

Page 5: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I. INTRODUCTION This is the third and last volume (Part III) of a series

of compilations of radiation damage test data published by the European Organization for Nuclear Research (CERN) on the results and experience gained there over the last l 0 years, particularly during the construction and operation of the 450 GeV Super Proton Synchro­tron (SPS).

Part I I) contains data on commercially available cable-insulating materials, a list of which can be found in Appendix l. The test samples were supplied by some 30 European cable manufacturers in the form of moulded plates, from which tensile test samples (ISO/R 3 7, ISO/R 527) were cut. The degradation of the mechanical properties and Shore hardness (ISO 868) are reported as a function of the absorbed dose in the range of 5 X l os to 5 X 106 Gy. As an end-point criterion for an elastic cable-insulating material, we consider it to be radiation resistant up to a dose at which the elongation at break is l 00% or more.

Part II 2> contains thermosetting and thermoplastic resins, with the exception of cable-insulating materials (see Appendix l). Most of the data have been obtained from epoxy resins used as insulation for large high­energy accelerator magnet coils. Again, mechanical pro­perties have been recorded as a function of the absorbed dose in the range of 5 X 106 to l X 108 Gy but, in the case of rigid plastics, flexion tests (ISO 178) have been carried out. As an end-point criterion we require that at a given dose D the ultimate flexural strength of the mate­rial is 50% or more of the initial value at zero dose. The electrical properties have not been tested, since usually the permanent effects only become important at doses where the mechanical damage is already severe.

The present Part III contains all items which did not fit into the two previous ones, e.g. cable ties, glass, hoses, motors, oils, paints, relays, scintillators, seals, etc. The items for the irradiation tests either have been supplied by firms from whom CERN had intentions of buying certain items containing materials that were par­ticularly sensitive to radiation, or they have simply been taken from the CERN stock without particular choice of material and supplier. In addition, tables of general rela­tive radiation effects (see Appendix 5) and cross­references to the main entries of all three volumes are given, as will be explained in Section 3. Therefore the pre­sent volume can be used as a guide to information con­tained in the whole series of data compilations.

Contrary to Parts I and II, where irradiation and test procedures could be carried out in accordance with IEC Standard 544 31 for insulating materials, the variety of materials and components presented here had to be irradiated and tested in a specific non-standard way depending on size, composition, and functions. Also, the critical test parameters are often only vaguely

1. INTRODUCTION Ce volume est le troisieme et dernier (IIJC partie) d'une

serie de publications de resultats d'essais de radio­resistance des materiaux obtenus a !'Organisation Europeenne pour la Recherche Nucleaire (CERN) au moyen d'essais effectues au cours des dix dernieres annees, en particulier pendant la construction, puis le fonctionnement, du super synchrotron a protons de 450 GeV (SPS).

La premiere partie11 traite de la radioresistance des materiaux utilises comme isolants pour les cables elec­triques. Une liste alphabetique de ces materiaux se trouve ici dans l'appendice l. Environ trente fabricants europeens de cables ont fourni Jes echantillons pour ces essais, sous forme de plaques moulees. Les proprietes mecaniques (resistance a la traction ISO/R 3 7, ISO/R 527) et la durete Shore (ISO 868) sont presentees en fonction de la dose absorbee, pour une gamme de doses allant de 5 X 10s a 5 X 106 Gy. Dans notre defi­nition du critere de degradation, nous considerons un isolant de cable radioresistant si, a une dose seuil don­nee, l'allongement a la rupture est encore egal OU supe­rieura 100%.

La seconde partie21 contient les resultats concernant les resines thermodurcissables et thermoplastiques, a !'exception des isolants de cables (voir appendice l). Dans la plupart des cas, ii s'agit de resines epoxydes utilisees pour !'isolation des bobines d'aimant pour les accelerateurs a haute energie. Les proprietes meca­niques sont de nouveau donnees en fonction de la dose absorbee, pour une gamme de doses allant de 5 x 106 a 1 X 108 Gy; dans le cas des plastiques rigides, nous avons effectue des tests de flexion (ISO 178). Le critere de degradation choisi exige qu'a une dose seuil D, la resistance a la flexion du materiel soit encore superieure OU egale a 50% de la valeur initiale a dose zero. Nous n'avons pas etudie Jes proprietes electriques car, en general, elles commencent a changer a des doses OU les degradations mecaniques sont deja tres importantes.

Le present volume (troisieme partie) contient tousles objets et produits que l'on ne pouvait inclure dans les catalogues precedents, par exemple !es ligatures de cables, le verre, Jes tuyaux, les moteurs, les huiles, les peintures, les relais, les scintillateurs, les 0-rings, etc. Les objets a soumettre aux tests d'irradiation provien­nent de l'une ou l'autre de deux sources: ou bien ils ont ete confies par des firmes auxquelles le CERN avait !'in­tention d'acheter des objets contenant des materiaux particu[ierement radiosensibles, OU bien ils ont ete pris aux stocks du CERN sans qu'il ait ete fait un choix par­ticulier du materiau ou de sa provenance. Nous presen­tons en outre des tableaux qui donnent les effets des radiations en general (voir appendice 5), ainsi que les references des sujets principaux traites dans les trois volumes, comme nous l'expliquerons dans la section 3.

Page 6: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

defined, and in some cases we had to restrict ourselves to operational tests or to visual inspections. The methods of irradiation and testing will be discussed in more detail in Sections 2 and 3. In some cases, the tests have been performed by specialists interested in the application (see references). We are grateful to them for having made their results available for this publication.

The entries in this series of data compilation cover a large spectrum of materials and components used in high-energy accelerator engineering; however, this list is still far from complete. Also, because of the extended period of about I 0 years during which the data were being collected, several items may have become obso­lete, or they are no longer available on the market. Nevertheless, the data presented could provide easily accessible information for the use of design engineers when selecting materials or when deciding whether further radiation damage tests have to be carried out.

As to the future project to build at CERN a large elec­tron/positron storage ring (LEP), we should make it clear that all information contained in these three volumes on organic materials, representing the highest number of entries, is also valid for the radiation environ­ment around this new installation. This is due to the fact that for organic materials the damage is to a large extent related to the absorbed dose irrespective of the type of radiation41• For inorganic substances, e.g. semiconduc­tors and metals, this is not true, and great care must be taken ifthe radiation field in an application is different to the one during the radiation test. At this point we would like to stress that electronics components are amongst the most radiation-sensitive items used in accelerator engineering. Although electromagnetic radiation, which will be the main contribution to the absorbed dose at LEP, may cause up to I 00 times less damage to semi­conductors than would particle radiation from proton accelerators or neutrons from a nuclear reactor51, this has to be seriously considered. A data compilation6>, made for European space projects, of the effects of elec­tromagnetic radiation on electronic components is avail­able and can be consulted for reference purposes.

2. IRRADIATION CONDITIONS As mentioned in the Introduction, the irradiation con­

ditions depend on the size, composition, and function of the item to be tested. Basically we used three radiation sources for this series of investigations: - the 7 MW ASTRA pool reactor at Seibersdorf,

Austria; - 60Co irradiators or SIJent-fuel elements; - dump and target areas of the CERN accelerators. Table I 7- 111 gives a summary of the characteristics of the various irradiation sources and their positions, and indicates which items have been irradiated there.

2

Par consequent, nous pouvons considerer cette partie comme un guide des informations contenues dans la serie complete.

Dans Jes Parties I et II, les irradiations des materiaux isolants ont ete effectuees en accord avec la norme IEC 544 3>, Dans le cas present ceci n'etait pas possible a cause de la diversite des materiaux et composants qui ont ete irradies et testes selon leurs dimensions, leur composition et leurs utilisations. Souvent les para­metres des essais ont ete insuffisamment definis et on a du se restreindre a de simples tests d'observation et d'inspection visuelle. Les sections 2 et 3 seront consa­crees aux methodes d'irradiation et d'essais. Dans cer­tains cas, Jes tests ont ete executes par des specialistes qui etaient interesses a !'application d'un materiau (voir les references citees). Nous les remercions ici d'avoir mis leurs resultats a notre disposition.

Les elements de cette serie de compilations represen­tent un grand nombre de materiaux et composants utili­ses dans la construction des accelerateurs a haute energie; neanmoins, on ne peut considerer cette liste comme complete. D'autre part, ii faut tenir compte du fait que ces resultats ont ete recueillis en une dizaine d'annees de travaux, et ii n'est pas exclu que certains objets ne soient plus presents sur le marche. Malgre cet inconvenient les resultats presentes ici peuvent fournir aux ingenieurs des indications utiles et facilement accessibles pour choisir des materiaux ou pour prendre, dans certains cas, la decision d'effectuer des essais de radiation supplementaires.

En ce qui concerne le nouveau projet de construction au CERN d'un anneau de stockage a electrons/posi­tons (LEP), on peut souligner que toutes les informa­tions contenues dans ces trois volumes sur Jes mate­riaux organiques (qui representent de loin la branche la plus importante), restent utilisables pour les champs de radiation dans cette nouvelle installation. En effet, Jes dommages occasionnes aux materiaux organiques varient, dans la plupart des cas, en fonction de la dose absorbee et sont independants de la nature des radia­tions4> . En revanche, pour les composes inorganiques, par exemple semi-conducteurs et metaux, cette remar­que n'est pas forcement exacte: ii faut done etre tres pru­dent dans le cas oil le champ de radiation pendant le fonctionnement est different de celui utilise pour le test. Sur ce point nous aimerions attirer !'attention de l'utili­sateur sur le fait que les composants electroniques sont parmi les objets les plus radiosensibles dans la cons­truction des accelerateurs. Dans la machine LEP, la ma­jeure partie des rayonnements sera du type electro­magnetique qui, on le sait par experience, peut causer jusqu'a 100 fois moins de dommages aux composants electroniques que les rayonnements issus d'accelera­teurs a protons OU de reacteurs nucleaires5

). Toutefois, ii faut etre tres attentif et nous citerons comme reference

Page 7: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Most of the materials have been irradiated in the nuclear reactor. This radiation source has the advan­tage of having a well-defined radiation field, reliable dosi­metry methods, and sufficiently high dose rates and therefore short irradiation times. A detailed survey of the irradiation positions and dosimetry methods at the ASTRA reactor can be found elsewhere 1>.

Spent-fuel elements (or switched-off reactor) and 6°Co irradiations were preferred for items with metallic parts which would have become too radioactive after irradiation in a reactor or a high-energy accelerator field. The radiation-sensitive parts within these items were, of course, the organic materials.

Irradiations around the CERN accelerators were carried out in only a very limited number of cases, the main reasons for this being the low dose rates, high dose gradients, imprecise knowledge of the particles and their energy spectra, and difficult dosimetry. Some parasitic irradiations were carried out on electronics components and on insulating materials, near dumps and target sta­tions, in order to study the effect of the radiation field and the dose rate.

The aim of the tests presented in this compilation was to predict the lifetime of the materials and components used in a radiation environment, prior to their installa­tion and operation. Therefore these types of tests are accelerated ones, where the integrated total dose is col­lected over a period ranging from hours up to three weeks, whereas the same dose, during operation, would be accumulated after periods usually exceeding 10 years.

It is known that radiation damage to organic materials may depend not only on the absorbed dose but also on the irradiation time and dose rate 12

-14>, The amount of

oxygen available by diffusion into the sample, in relation to the number of radiation-produced chemically reactive radicals, or chain scission sites, may strongly influence the amount of permanent damage to the material. There­fore the damage caused by irradiation over a long period of time may be more important than damage from irradiation to the same total dose, at high dose rates for a short time. The dose rate effect is, in addition, depen­dent on the chemical structure of the material itself. The amount of oxygen available is a function of the sample thickness and of its permeability for gases, and of the amount of stabilizers added to the polymer to control oxidation damage under normal ageing conditions. For example, it is known that the effect is more pronounced in polyolefins [e.g. polyethylene (PE)], but is usually not of great importance for polyvinylchloride (PVC) and ethylene-propylene rubber (EPR).

Finally, we draw the attention of the user of this cata­logue to the different dosimetry methods as listed in Table I for the various radiation sources. Only the calorimetric method yields a direct measure of the

une compilation6> des effets de radiation par rayonne­

ment electromagnetique sur Jes composants electroni­ques, editee pour des projets spatiaux europeens.

2. CONDITIONS D'IRRADIA TION Comme mentionne dans !'introduction, les conditions

d'irradiation dependent des dimensions, de la composi­tion et des utilisations possibles des objets testes. Nous avons principalement utilise trois modes d'irradiation: - Le reacteur piscine ASTRA, de 7 MW, a Seibersdorf

(Autriche); - Une source de cobalt ou de combustible use d'un

reacteur; - Des zones de cibles et des arrets de faisceau des

accelerateurs du CERN. Le tableau l 7-

11) presente un resume des caracteris­

tiques de ces differentes sources d'irradiation, ainsi que Jes positions d'irradiation avec indication des positions choisies pour !es differents objets a tester.

La plupart des materiaux ont ete irradies dans le reac­teur nucleaire. Cette source d'irradiation a l'avantage de posseder un champ de radiation bien defini, une methode dosimetrique fiable et des debits de dose suffi­samment eleves pour permettrer des temps d'irradiation assez courts. Les details sur Jes positions d'irradiation et la dosimetrie au reacteur ASTRA ont ete presentes ailleurs 7l.

Les combustibles du reacteur (ou reacteur eteint), ainsi que la source de cobalt, sont utilises de preference pour irradier les objets contenant des parties metal­liques qui deviendraient trop radioactives dans un reac­teur ou un accelerateur en fonctionnement. Les parties radiosensibles de ces objets sont, bien entendu, Jes composants organiques.

Nous n'avons effectue des irradiations autour des accelerateurs du CERN que dans tres peu de cas. Les principales raisons en sont un faible debit de dose, un gradient de dose eleve, une dosimetrie difficile et une mauvaise connaissance du spectre des particules et de leur energie. Quelques irradiations isolees ont ete effec­tuees aupres des arrets de faisceau et stations de cible sur des composants electroniques ainsi que sur des materiaux isolants, avec pour but l'etude des effets du champ de rayonnement et du debit de dose.

Le but de tous !es essais presentes dans cette compi­lation est de predire, avant leur installation et leur uti­lisation, le temps de vie ou de fonctionnement des materiaux et composants utilises dans un champ de radiation. Par consequent, ces types d'essais sont des essais acceleres, OU !'on distribue la dose totale integree au cours d'une periode qui peut aller de quelques heures a trois semaines, alors que !es memes doses, pendant le fonctionnement reel, seront accumulees en general au bout de periodes depassant dix ans.

3

Page 8: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

absorbed dose, whereas all the other doses were ob­

tained by intercalibration. All doses in this report are

quoted in gray (Gy) for a (CH 2)n-type material (I Gy = I J ·kg- 1 = 102 rad). For non-organic materials, e.g.

semiconductors, this does not represent the true dose

but serves as a comparative measure of exposure. If the true dose is needed for comparison with other data, it

can be calculated from this by the methods described in

Refs. 3 or 15, for example, if the atomic composition of

the material is known.

3. PRESENTATION OF RESULTS As demonstrated in the previous section, it is evident

that in the complex field of radiation damage to mate­

rials a great number of parameters may influence the

results, especially if a large variety of materials are

tested and the doses range over six decades. Therefore the information presented has to be used with precaution

and in many cases it can serve as a guideline only. We are confident, however, from the experience that we have

gained over the last I 0 years, that we can predict the expected lifetime of materials in a high-energy accele­

rator environment, within the right order of magnitude,

using the results from our accelerated reactor tests. If the results for different items made of the same base

material are found to differ, this may be due to a specific

composition or test condition. Furthermore, the func­tion of the items may require different degrees of per­

formance from the base material, and therefore different appreciations of the radiation resistance may result.

As in the two preceding volumes, the data are pre­sented in alphabetical order, and the following informa­

tion can be found for tested materials or components: - the keyword used to describe the entry;

- most radiation-sensitive base material used in the composition of the test item, followed by type, sup­

plier, and an internal identification;

- a short description of the material;

- its application or use at CERN, if known;

- irradiation conditions specifying the radiation source,

the medium, the dose rate, and the total integrated

doses received by the material; - the methods of testing, a short description, and the

test standard if applicable; - a summary of the results of tests; more details, when

available, will be found on the opposite (left-hand)

page. - remarks, if any; - references 16-m to where further data or information

on this entry may be found; - a general appreciation, illustrating graphically the

dose range in which no damage (blank), light to mod­

erate damage (hatched), and/or moderate to severe damage (black) can be expected. It is also indicated if

4

II faut noter que les effets des radiations sur !es

materiaux organiques ne dependent pas uniquement de

la dose absorbee mais aussi du temps d'irradiation et du debit de dose 12

-14J_ La quantite d'oxygene disponible par

diffusion dans l'echantillon, en relation avec le nombre

de radicaux chimiquement actifs durant !'irradiation, qui sont des positions de rupture de chaines, peuvent forte­

ment influencer les dommages subis par les materiaux.

II en resulte que Jes dommages causes au cours d'une

tongue periode d'exposition peuvent etre plus

importants que ceux causes, a meme dose integree, par

des debits de dose eleves durant une courte periode. De plus, la structure chimique du materiel influence cet effet

de debit de dose. La disponibilite en oxygene est une fonction de l'epaisseur de l'echantillon, de sa permeabi­

lite aux gaz et de la quantite de stabilisateurs presents dans le polymere pour contr61er Jes dommages par oxy­

dation au cours du processus normal de vieillissement. Ainsi, ii est connu que cet effet est plus important pour

Jes polyolefines [par exemple le polyethylene (PE)) que pour le chlorure de polyvinyle (PVC) ou le caoutchouc

ethylene propylene (EPR). Enfin, nous attirons )'attention de l'utilisateur de ce

catalogue sur les differentes methodes dosimetriques

presentees au tableau I, et qui sont utilisees pour des

sources d'irradiation differentes. Seule la methode

calorimetrique offre une mesure directe de la dose

absorbee, alors que toutes Jes autres doses sont obte­nues par intercalibration. Toutes Jes doses mentionnees

dans ce catalogue sont donnees en gray (Gy) pour un materiel du type (CH2)n (1 Gy = I J · kg- 1 = 102 rad).

Pour les materiaux inorganiques, semi-conducteurs par exemple, ceci ne represente pas la dose exacte; nous

gardons cependant cette unite pour des motifs de com­paraison des expositions. Si l'on a besoin de la dose reelle, pour des comparaisons avec d'autres donnees,

pour autant que la composition atomique du materiel

soit connue, on peut la calculer d'apres nos valeurs en

utilisant les methodes decrites dans Jes references 3 et

15, par exemple.

3. PRESENTATION DES RESULTATS Comme signale plus haut, ii est evident que Jes effets

des radiations sur Jes materiaux sont tres complexes,

un grand nombre de parametres pouvant influencer les resultats; cette complexite est due, en particulier, a la

grande diversite des materiaux testes ainsi qu'a la gamme de dose etendue sur six ordres de grandeur.

L'information presentee doit done etre utilisee avec pre­caution et, dans bien des cas, elle ne doit etre consideret

que comme une ligne a suivre. Grace a !'experience que nous avons acquise en dix ans, nous pouvons toutefois predire avec un ordre de grandeur correct, a partir des

resultats de nos essais acceleres en reacteur, la duree de

Page 9: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

the appropriate range was not reached in our test or in the test of an equivalent material contained in this catalogue.

A more detailed description of these data sheets is given in Appendix 7.

As mentioned in the Introduction, the materials pre­sented in this series of catalogues are listed in Appen­dix I. Table 2 gives the French names with their English translation, and the trade names. Appendix 2 gives explanations of trade names and popular names. Appendix 3 lists the firms who collaborated in our ra­diation test programme, and Appendix 4 explains the abbreviations which occur in this volume.

4. GENERAL COMPARATIVE RESULTS OF RADIATION EFFECTS

All the entries mentioned in Section 3 refer to a speci­fic material, component, or device. In addition, Appendix 5 gives a review of general relative radiation effects, in the form of tables or graphs, under the follow­ing entries 1

•2

•36

•37>:

- cable insulations, - elastomers, - G-values (radio-chemical yield), - hoses, - oils, - paints, - textiles, - thermoplastic and thermosetting resins. Appendix 5 begins with a complete list of all materials quoted in these tables; cross-references to the tables are also given in the alphabetical data compilation section.

Further information on radiation damage to materials and components that might be of interest to the reader can be found elsewhere6

•38

-44>.

5. CLASSIFICATION OF MATERIALS In Appendix 6 we classify the main materials and

entries contained in these three volumes, under the fol­lowing categories: - use not recommended, or to be used with precaution,

usable up to 5 X 105 Gy, usable up to 1-2 X 106 Gy, usable up to 1-2 X 107 Gy, usable up to l X 108 Gy, usable above l X 108 Gy. Following the remarks in Sections 2 and 3, the aim of

this classification is to indicate to the user the dose limit up to which the various materials may be used. It should again be stressed that the limits are specific to the item tested and to the end-point criteria applied, and that it may be possible to obtain higher or lower dose toler­ances for differently designed applications of the same type of material. Nevertheless, our experience shows

vie des matenaux utilises aupres des accelerateurs de haute energie. II est possible que Jes resultats obtenus pour differents objets fabriques avec la meme matiere de base soient differents; ceci peut etre explique par des compositions ou des conditions d'essais specifiques differentes. De plus, !'utilisation de ces objets peut demander des degres differents de performance a la matiere de base; ii en resulte une appreciation differente de la radioresistance.

Comme dans les deux volumes precedents, Jes resul­tats sont presentes ici par ordre alphabetique en anglais; sur chaque page on peut trouver les informa­tions suivantes: - Nom-clefidentifiant l'objet decrit; - Materiaux de base radiosensibles constituant l'objet

de l'essai, suivi du type, du nom du fournisseur et du numero d'identification interne;

- Breve description du materiau ou de l'objet; - Application ou utilisation au CERN si connues; - Conditions d'irradiation specifiant la source, le

milieu, le debit de dose et Jes doses totales m;ues par le materiau;

- Methodes d'essais, breve description, norme si appli­cable;

- Resume des resultats obtenus; on peut trouver sur la page en face (page de gauche) un supplement d'infor­mation chaque fois que cela est possible;

- Remarques, s'il ya lieu; - References 16

-35>, si !'on desire connai'tre plus de

details sur cet obj et; - Appreciation generale, montrant graphiquement la

gamme de doses pour laquelle Jes dommages sont nuls (blanc), moderes (hachure) et severes (noir); par­fois aussi, indication (no test) de la zone susceptible d'etre degradante mais ou nous n'avons pas fait d'es­sais sur le materiau lui-meme ou un materiau equiva­

lent. Une description plus detaillee de ces feuilles de don­

nees est presentee a l'appendice 7. Comme nous l'avons dit dans !'introduction, tous Jes

materiaux mentionnes dans cette serie de catalogues constituent l'appendice 1. Pour retrouver facilement un materiau dont on connait le nom uniquement en fran­\:ais, le tableau 2 liste tous Jes materiaux cites dans ce volume en ordre alphabetique en frarn,:ais, avec leur tra­duction anglaise.

L'appendice 2 donne les explications des noms depo­ses OU commerciaux. L'appendice 3 presente la liste des firmes qui ont collabore dans nos essais de radioresis­tance, l'appendice 4 explique les abreviations.

4. RESULTATS GENERAUX COMPARATIFS DES EFFETS DE L'IRRADIA TION

Tous Jes elements de la section 3 designent un mate­riau ou appareil bien determine. L'appendice 5 se

5

Page 10: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

that the mechanical damage to a base material is con­sistent in relation to the dose, and that radiation-sensi­

tive materials such as Teflon must not be employed after they have reached their respective dose limit.

6

compose d'une serie d'informations generales sur les ef­fets des radiations, sous forme de tableaux ou graphi­

ques, pour !es objets suivants 1•2

•36

•37 l:

- Isolants de cables, - Elastomeres, - Valeur G (rendement radiochimique), - Tuyaux, - Huiles, - Peintures, - Textiles, - Resines thermoplastiques et thermodurcissables.

Avant ces tableaux, nous avons introduit une liste de taus les materiaux qui y sont mentionnes. D'autre part, dans la partie alphabetique, des renvois aux tableaux de cet appendice 5 sont faits chaque fois qu'il ya lieu.

Des informations supplementaires sur les effets des radiations qui pourraient interesser l'utilisateur sont citees sous Jes references 6 et 38-44.

5. CLASSIFICATION DES MATERIAUX Dans l'appendice 6, taus Jes materiaux et objets con­

tenus dans Jes trois volumes sont classes dans les cate­gories suivantes: - Utilisation non recommandee, ou avec precaution, - Utilisable jusqu'a 5 X 105 Gy, - Utilisablejusqu'a 1-2 X 106 Gy, - Utilisablejusqu'a 1-2 X 107 Gy, - Utilisablejusqu'a I X 108 Gy, - Utilisable au-dessus de I X 108 Gy. Suivant les remarques des sections 2 et 3, le but de cette classification est de donner l'ordre de grandeur de la

dose limite jusqu' a laquelle un materiau peut etre utilise. II faut de nouveau souligner que ces limites sont speci­

fiques aux objets testes et aux criteres de fin d'utilisa­tion choisis. II est possible d'obtenir des performances plus faibles OU plus eJevees suivant Jes differentes appli­cations proposees pour un meme type de materiaux. Toutefois, nous avons remarque par experience que !es dommages mecaniques subis par un materiau de base sont en rapport avec la dose; des materiaux sensibles au rayonnement, comme par exemple le Teflon, ne devront en aucun cas etre utilises au-dela de leur limite de dose respective.

Page 11: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Acknowledgements

The present study was initiated by J.B. Adams with the start of the SPS programme and was originally carried out in collaboration with M. Van de Voorde and the JSR Division. The radiation damage test studies have been continuously supported by A.J. Herz (HS Department).

Our particular thanks are due to K. Goebel for his in­terest in this work and for many useful discussions and suggestions.

We would like to thank the firms which have supplied the test samples, both for their interest in this subject and for useful discussions which we had with their re­presentatives.

The irradiations have been carried out at the ASTRA reactor centre, which belongs to the Osterreichische Stu­diengesellschaft fiir Atomenergie in Vienna. The good collaboration with A. Burtscher and J. Casta is acknow­ledged.

These irradiation tests were carried out at the request of numerous colleagues at CERN. We are grateful to them for supplying us with samples and information, and, in many cases, conducting the material tests and making the results known to us. They also cross­checked the information presented in this publication. This data compilation depended to a large part on their collaboration.

Finally, we would like to acknowledge the special effort and care taken by the CERN Scientific Reports Editing and Text Processing Sections in the preparation of this document.

Remerciements

Cette etude a ete lancee par J.B. Adams, avec le debut du programme SPS; initialement, elle a ete effectuee en collaboration avec M. Van de Voorde et la Division JSR. Les etudes de degradation des materiaux due au rayon­nement ont ete constamment soutenues par A.J. Herz (Departement HS).

Nous remercions particulierement K. Goebel pour l'interet qu'il a montre pour cette etude et pour de nom­breuses suggestions et discussions.

Nous tenons aussi a remercier les fabricants qui ont fourni des echantillons d'essais; nous avons eu des dis­cussions utiles avec les representants de nombreuses firmes.

Les irradiations ont ete effectuees au reacteur ASTRA, a Seibersdorf, en Autriche, qui fait partie de l'Osterreichische Studiengesellschaft fiir Atomenergie. Nous avons apprecie la bonne collaboration que nous

ont ofTerte A. Burtscher etJ. Casta. Ces tests d'irradiation ont ete executes a la demande

de nombreux collegues au CERN. Nous leur sommes reconnaissants de nous avoir fourni des echantillons et des informations, et d'avoir, dans de nombreux cas, re­alise eux-memes Jes tests sur Jes materiaux, mettant leurs resultats a notre disposition. Ils ont aussi verifie Jes informations presentees dans cette publication. Cette compilation de donnees a dependu en grande par­tie de leur collaboration.

Nous voudrions enfin exprimer notre appreciation de !'effort et de !'attention que les sections Edition de rap­ports scientifiques et Traitement de textes du CERN ont apportes a la preparation de ce document.

7

Page 12: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

REFERENCES

I) H. Schonbacher and A. Stolarz-Iiycka, Compilation of radiation damage test data, Part I: Cable insulating materials, CERN 79-04 ( 1979).

2) H. Schanbacher and A. Stolarz-Iiycka, Compilation of radiation damage test data, Part II: Thermosetting and thermoplastic resins, CERN 79-08 ( 1979).

3) Guide for determining the effects of ionizing radiation on insulating materials, IEC Standard 544 (3 parts) (Inter­national Electrotechnical Commission, Geneva, 1979).

4) D.C. Phillips, The effects of radiation on electrical in­sulators in fusion reactors. AERE-R 8923, Harwell ( 1978).

5) K.P. Lambert, H. Schonbacher and M. Van de Voorde, A comparison of the radiation damage of electronic compo­nents irradiated in different radiation fields, Nucl. Instrum. Methods 130, 29 l (1975). See also CERN 75-4 (1975).

6) F. Wulf, D. Braunig and W. Gaebler, Data compilation of irradiation tested electronic components, Hahn-Meitner Inst. report HMl/B 353, TN 53/08, 2nd edition ( 1981).

7) H. Schonbacher, M. Van de Voorde, A. Burtscher and J. Casta, Study on radiation damage to high energy accelerator components by irradiation in a nuclear reac­tor, Kerntechnik 17, 268 ( 1975).

8) S. Battisti, R. Bossart, H. Schonbacher and M. Van de Voorde, Radiation damage to electronic components, Nucl. Instrum. Methods 136, 45 l (l 976); see also: CERN 75-18 (1975) (also translated into Russian).

9) B. McGrath, H. Schonbacher and M. Van de Voorde, Effects of nuclear radiation on the optical properties of cerium-doped glass, Nucl. Instrum. Methods 135, 93 (1976); see also: CERN 75-16 (1975).

10) B. McGrath, H. Schonbacher and M. Van de Voorde, Effect of neutron radiation on the electrical resistivity of copper at room temperature, Nucl. Instrum. Methods 136,575(1976).

11) A. Iiycka and H. Schonbacher, High-level dosimetry for radiation damage studies at high-energy accelerators, Proc. 3rd ASTM-EURATOM Symp. on Reactor Dosi­metry, Ispra, 1979 (EUR 68 l 3, Ispra 1980), p. 316.

12) H. Wilski, Verhalten eines Athylen-Propylen-Copoly­merisats bei der Einwirkung ionisierender Strahlen in Luft, Colloid & Polym. Sci. 254, 451 ( 1976).

13) R.L. Clough and K.T. Gillen, Radiation-thermal degra­dation of PE and PVC: Mechanism of synergism and dose rate effects, Radiat. Phys. and Chem. 18, 66 l (l 981).

14) I. Kuriyama, N. Hayakawa, Y. Nakase, J. Ogura, H. Yagyu and K. Kasai, Effect of dose rate on degrada­tion behavior of insulating polymer materials, IEEE Transact. on Electr. Insulation EI 14, 272 ( 1979).

15) M.H. Van de Voorde, Effects of radiation on materials and components - Megarad dosimetry, CERN 69-12 ( 1969).

16) D.C. Phillips, J.M. Scott, K. Goebel, H. Schanbacher. W. Dieterle, W. Eichenberger and J. Maurer, The selec­tion and properties of epoxide resins used for the insula­tion of magnet systems in radiation environment, CERN 81-05 ( 198 l ).

17) D. Johnson, Material radiation resistance and the SPS radiation field, CERN EP/SCE-R 703T/UA5/P80-l ( 1980).

18) P. Beynel, Tenue aux rayons ionisants des materiaux iso­lants sous forme de bande autoadhesive, CERN Lab II­RA/TM 75-5 ( 1975).

19) P. Beynel, Tenue a !'irradiation des principaux materiaux composant un moteur electrique, CERN Lab II­RA/37.40/TM 74-26(1974).

8

20) P. Beynel, Tenue aux rayons ionisants des ligatures pour cables electriques, CERN Lab II-RA/TM 75-4 ( 1975). P. Beynel, Tenue a !'irradiation des ligatures AMP, CERN Lab II-RA/TM 75-32 ( 1975).

21) H. Schonbacher, K.P. Lambert and M. Van de Voorde. The effect of mixed radiation fields on electronic devices, CERN preprint Lab II/RA/PP 74-4, Int. Conf. on Evaluation of Space Environment on Materials, Toulouse, 1974 (CNES, Toulouse, 1974).

22) G. Villard, Essai de tenue en haute tension de liquides didectriques. CERN Lab 11/BT/GT/aw/E, Techn. Note/74-2 ( 1974).

23) R. Dubois, Fonctionnement en electrostatique pour !'extraction 1976-decembre 1977. CERN Tech/78-3 ( 1978).

operation du septum Ouest, periode juillet

SPS/ ABT /RD/Note

24) R. Dubois, Fonctionnement en operation des septa electrostatiques en 1978 (Extractions Ouest et Nord), CERN SPS/ ABT /RD/Note Tech/79-4 ( 1979).

25) P. Beynel, Tenue aux radiations d'un eclairage de secours au neon, CERN HS-RP/TM 77-66 ( 1977).

26) D. Bend!, J. Casta and H. Kurz, Messung der Anderung der magnetischen Eigenschaften von lamellierten Ring­kernen durch Neutronenbestrahlung im ASTRA­Reaktor, ASTRA Reaktor Inst. report, REX 123 ( 1974).

27) H. Beger, Radiation induced attenuation in some com­munication glass fibres around 850 and 1060 nm, CERN-SPS/ARF/77-21 (1977).

28) H. Schonbacher, M. Van de Voorde, G. Kruska and K.M. Oesterle, Performance of paint coatings in the radiation field of nuclear reactors and of high energy par­ticle accelerators, and after contamination by radio­nuclides, Kerntechnik 19, 209 ( l 977).

29) H. Schonbacher and W. Witzeling, Degradation of acrylic scintillator and wavelength shifter material by nuclear radiation, Nucl. Instrum. Methods 165, 517 ( 1979).

30) D. Johnson, Irradiation study of film, mylar and scintil­lator, CERN/EP/JD/ed, 21.6.1979 (unpublished).

31) P. Beynel, Note concernant l'etablissement d'un ensemble d'essais systematiques de resistance mecanique de 0-ring subissant des irradiations, CERN Lab 11/RA/3 7.04/TM/73-14 (1973).

32) P. Beynel, Note sur la tenue a !'irradiation des joints 0-ring, CERN Lab II/RA/TM 75-42 ( 1975).

33) C. Mueller, P. Siffert and H.M. Heijne, Defects introduc­ed in silicon by irradiation with muons of GeV energy, Proc. Int. Conf. on Radiation Effects in Semiconductors, Dubrovnik, 1976, eds. N.B. Urli and J.W. Corbett (The Institute of Physics, Bristol and London, 1977), p. 505. E. Heijne, Radiation damage: Experience with silicon detectors in high-energy particle beams at CERN, Proc. of Meeting on Miniaturization of High-Energy Physics Detectors, Pisa, 1980 (Plenum Press, London, 198 l ).

34) P. Beynel and A. Ijspeert, Resultats d'un essai d'irradia­tion nucleaire sur !es parties isolantes d\rn microrupteur utilise pour !es interlocks des aimants splitters, CERN Technical note SPS/ ABT/TA/ AI/79-193 ( 1979).

35) P. Beynel, Resistance aux radiations des materiaux de construction du sas du puits de secours neutrino (SPS), CERN HS-RP/TM/78-64 ( 1978).

36) M.H. Van de Voorde, Effects of radiation on materials and components, CERN 70-5 ( 1970).

37) M.H. Van de Voorde and C. Restat, Selection guide to organic materials for nuclear engineering, CERN 72-7 ( 1972).

38) Proc. IEEE Annual Conferences on Nuclear and Space Radiation Effects, published in IEEE Trans. Nucl. Sci.

Page 13: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

39) L.L. Bonzon, An experimental investigation of syner­gisms in class I components subjected to LOCA type­tests, NUREG/CR-0275, SAND 78-0067 (Sandia Laboratories, Albuquerque, N.M., USA, 1978).

40) C.L. Hanks and D.J. Hamman, Radiation effects design handbook - Section 3: Electrical insulating materials and capacitors (NASA CR 1787, Washington, 1971).

41) A. Spencker, H.G. Wagemann and D. Braunig, Strahlen­belastungsuntersuchungen an elektronischen Bauele-

menten des SYMPHONIE-Satelliten, Hahn-Meitner Institute report HMI-B 181 (1975).

42) D.S. Billington and J.H. Crawford Jr., Radiation damage in solids (University Press, Princeton, 1961 ).

43) J .F. Kircher and R.E. Baumann, eds., Effects of radiation on materials and components (Reinhold, New York, 1964).

44) R.O. Bolt and J.G. Carrol, eds., Radiation effects on organic materials (Academic Press, New York. 1963).

9

Page 14: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

0

Table I

Characteristics of various radiation sources used for this data compilation

Radiation source

7MWASTRA research pool reactor

Fuel clements ASTRA

0°Co source

CERN accelerators

Irradiation position•)

Pos. 11

Ebene I (El)

SNIF

Core

Pos. 35

Various

ISR beam dump

SPS neutrino target area

PSorSPS ring

Characteristics of radiation field

5 X 1016 n,h/m2 s 3 X 1016 nr(E >I MeV)/m 2 s

4 X JO'l n1h/m2 s 3 X J0 14 ni(E >I MeV)/m 2 s

2 X 1013 n,h/m2 s 5 X 10' 3 nr(E >I MeV)/m 2 s

IX JO'"n,h/m 2 s 8 X J017 nr(E >I MeV)/m 2 s

Gamma radiation field characteristic for reactor fuel elements (0.5-3 MeV)

Gamma rays 1.2 MeV

Hadron cascade and secondary gamma rays. Primary proton energy:;:; 30 GeV

Hadron cascade and secondary gamma rays. Primary proton energy:;:; 400 GeV

Primaries (losses) and secondaries up to 30 GeV (PS) or 250 GeV and 400 GeV (SPS)

a) Specified on each entry in the data compilation section.

Irradiation Irradiation medium temperature

(OC)

Water 40-50

Air 32-45

Air 35-45

Water or N2 or He 50-100

Air 25-35

Air :;:; 25

Air :;:;22

Air :;:; 23

Air :;:; 22

Dose rate Dosimetry method Items irradiated

(Gy/h)

2 x 106 Calorimeter 7) Thermosetting resins') Activation detector')

2 X JOs Ionization chamber') Cable-insulating materials 1);

other organic materials -------------

n:2 X 103 Activation detector Electronics components8), optical

y: 2 X 102 Ionization chamber glasses"'

3 x J06 Activation detectors Calorimeter Magnetic materials, copper wires' 01

IX 104

Ionization chamber 7) Insulating materials containing metal;

IX 10s hoses with metal connectors

l X 104 Fricke dosimeter Insulating materia!s containing metal; motor~

----~----- ---------

RPL and PDG glass Electronics components and items con-4 dosimeters 111 t&ining metal, up to 103 Gy

3 x JO' RPL and glass Cable and magnet insulations; items dosimeters") containing metal, up to 5 X Io• Gy

RPL and glass dosimeter, Cable and magnet insulation; paints; 1-10 ionization chambers 111 operational life-tests

Page 15: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

En fran\:ais

Absorbeur HF Accessoires de pompe a vide Acetate Acetate cellulosique Acetate d'ethylene vinyl Acetone Alcool polyvinylique Alkyl aromatique Amiante-ciment Aniline formaldehyde Araldite Askarel Benzene Bois Bromoforme Bromure d'ethyle Buna Caoutchouc acrylique Caoutchouc acrylonitrile Caoutchouc acrylonitrile-butadiene

Tableau 2

Noms, en ordre alphabetique, de to us Jes materiaux cites dans ce volume, avec leur traduction. sous laquelle on peut Jes trouver dans le catalogue.

Les noms en italiques sont des marques de fabrique ou des noms deposes, sous lesquels on les trouve dans le catalogue

Voir sous

HF absorber Vacuum pump accessory Acetate Cellulose acetate Ethylene vinyl acetate (EV A) Acetone Polyvinylalcohol Aromatic alkyl Asbestos cement Aniline formaldehyde

Askarel Benzene Wood Bromoform Ethyl bromide

Acrylic rubber Acrylonitrile rubber

C aoutchouc acrylonitrile-butadiene-styrene Caoutchouc de butyle

Acrylonitrile-butadiene rubber Acrylonitrile-butadiene-styrene rubber (ABS) Butyl rubber

Caoutchouc chlore Caoutchouc ethylene-propylene Caoutchouc polychloroprene Caoutchouc polyurethane Caoutchouc de silicones Caoutchouc styrene-butadiene Ceramique Chlorobenzene Chloroforme Chlorure de polyvinyle Chlorure de polyvinylidene Composants electroniques Composes lluores Connecteur Copolymere d'ethylene-tetralluoroethylene Dacron Detecteur de particules Detecteur silicone Dia/a C Dichlorobenzene Dichlorethane Dobeckot Dyne/ Eel air age Element de chaufTage Epikote Esters Esters cellulosiques Ethers Ethylene-chlorotrilluoroethylene Fer Fibre cellulosique Fibre optique Fibre de verre Fil de cuivre Fil electriq ue isole Fil electrique, cable Flamtrol Gaine thermoretractable Halar Hostalen Huile Huile chlorolluorocarbonee Huile lluoree Huile de graissage Huile isolante

Chlorinated rubber Ethylene-propylene rubber (EPR) Polychloroprene rubber (Neoprene) Polyurethane rubber (PUR) Silicone rubber Styrene-butadiene rubber (SBR) Ceramic C hlorobenzene Chloroform Polyvinyl chloride (PVC) Polyvinylidene chloride Electronics components Fluorinated compounds Connector Ethylene-tetralluoroethylene copolymer (ETFE)

Particle detector Silicon detector

Dichlorobenzene Dichloroethane

Lighting Heating element

Esters Cellulose esters Ethers Ethylene-chlorotrilluoroethylene (E-CTFE) Iron Cellulose fibre Optical fibre Glass fibre Copper wire Insulated wire Cable insulation

Thermoshrinking sheath

Oil Chlorofluorocarbon oil Fluorinated oil Lubricating oil Insulating oil

11

Page 16: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Huile minerale Huile phosphatee Huile de polyglykol Huile de silicate Huile de silicones Hypalon Hypermal/oy Hytrel Interrupteur Isolation de bobine d'aimant Isolation de cables Joint (cage de roulement) Joint d'etancheite Joint pour chambre it vide Kapton Kel-F Kevlar Kynar Laine Ligature de cables Lupo/en Makrolon Manchon isolant Materiel magnetique Melamine-formaldehyde Mi:thacrylate de polymethyl Micatherm Microrupteur Moteur electrique Mousse Mylar Neoprene Nomex Noryl Novolac Nylon 0-ring Orlon Oxyde d'aluminium Oxyde de polyphenylene Papier Peinture Peinture lumineuse Perbunan Perfluoroethylene-propyli:ne Pertinax Plexiglas Polyacryl Polyacrylonitrile Polyallomi:re ethylene-propylene Poly amide Polyamide aromatique Polybutadiene Polybutylene-terephtalate Polycarbonate Polychloroprene Polychlorotrifluoroethylene Polyester Polyethylene Polyethylene chlorosulfone Polyethylene reticule Polyhydanto'ine Polyimide Polyisobutylene Polymere fluore Polymeres vinyl-chlores Polyolefine Polyphenylene (oxyde de) Polyphenylene (sulfure de) Polypropylene Polysilicate de lithium Polysiloxane Polystyrene Pol ytetr afluoroethy li:ne Polyvinylbutyral Polyvinylformal Pyrofll Quartz Radox

12

Mineral oil Phosphate oil Polyglykol oil Silicate oil Silicone oil

Switch Magnet coil insulation Cable insulation Joint Seal ( 0-ring) Vacuum gasket

Wool Cable tie

Insulating sleeve Magnetic material Melamine-formaldehyde Polymethyl methacrylate (PMMA)

Microswitch Motor, electric Foam

Seal

Aluminium oxide Polyphenylene oxide Paper Paint Paint, luminescent pigment

Perfluoroethylene-propylene (FEP)

Polyacryl Polyacrylonitrile Ethylene-propylene polyallomer Poly amide Aromatic polyamide Polybutadiene Polybutylene-terephtalate (PBTP) Polycarbonate Polychloroprene (Neoprene) Polychlorotrifluoroethylene (Kel F) Polyester Polyethylene (PE) Chlorosulfonated polyethylene (CSP) Polyethylene cross-linked (XLPE) Polyhydantoin Polyimide Polyisobutylene Fluorinated polymer Vinyl chloride polymers Polyolefin Polyphenylene oxide Polyphenylene-sulfide Polypropylene Lithium polysilicate Polysiloxane Polystyrene Polytetrafluoroethylene (PTFE) Polyvinyl butyral Polyvinyl formal

Quartz

Page 17: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Rayonne Relais Resine Resine epoxy de Resine phenolique Resine de polyester Resine de silicones Resine thermodurcissable Resine thermoplastique Resistofo/ Ru ban Ru ban isolant Ryton Saran Scintillateur Silicate Soie Styrene Tableau terminal Teflon (PTFE) Tefze/ Tetrachlorure de carbone Terephtalate de polyethylene Toluene polyvinylique Tube de chambre a vide Tuyaux (tubes) Uree-formaldehyde Va/vata Vanne Vanne pour le vide Verre Verre dope au cerium Vestolene Vi ton

Rayon Relay Resin Epoxy resin Phenolic resin Polyester resin Silicone resin Thermosetting resin Thermoplastic resin

Tape Insulating tape

Scintillator Silica Silk Styrene Terminal board

Carbon tetrachloride Polyethylene terephthalate (PETP) Polyvinyl toluene Vacuum chamber tube Hoses Urea-formaldehyde

Valve Vacuum valve Glass Cerium-doped glass

13

Page 18: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX I

Names, in alphabetical order, of all materials for which test results are presented in these volumes. The main entries are in romans, the names in italics appear as cross-references.

Volume I: Cable insulating materials (Ref. I)

Butyl rubber Ch/orostop Chlorosulfonated polyethylene (CSP) Cross-linked polyethylene (XLPE) Desmopan Ethyl-acrylate rubber (EAR) Ethylene-propylene diene rubber (EPDM) Ethylene-propylene rubber (EPR) Ethylene vinyl acetate (EV A) Flamtrol F/uoropolymer Halar Hypalon Hytrel Kap ton Lupo/en Neoprene Nordel Polychloroprene Polyethylene (PE) Polyurethane (PUR) Polyvinyl chloride (PVC) Pyrofi/ Radox Semiconducting polyethylene Silicone rubber Silythene Stilan Teflon Tefzel Viton XLPE

Volume II: Thermoplastic and thermosetting resins (Ref. 2)

14

AralditeB AralditeD Araldite F and other Araldite resins Araldite F +Epoxy Novo/ac Birakrit Cevolit Crystie DobeckanIF Dobeckot

Epikote Epoxy resins Epoxy resins + Epoxy Novolac Etronax I so val Keri mid Kine/ Makro/on Novolac Orlitherm Phenolic resins Polycarbonate resins Polyester resins Polyimide resins Po/ylite Polyurethane resins Resofil Ryton Samicanit Samicatherm Silicone resins Veridur Vetresit Vetronit

Volume III: Accelerator engineering materials and components(present volume)

Adhesive tape Aluminium oxide Araldite Asbestos cement Askarel Buna Cable insulation Cable tie Ceramic Cerium-doped glass Connector Copper wire Dia/a C Diesteroil Electronic components Epoxy resin Ethylene-propylene rubber (EPR) and (EPDM) Ethylene-tetrafluoroethy/ene copolymer (ETFE) Fluorinated oil

Page 19: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Fluorinated polymer Foam Glass Glass fibre Heating element HF absorber Hoses Hostalen Hypermalloy Hytrel Insulated wire Insulating oil Insulating sleeve Insulating tape Iron Joint Kapton

Kevlar Kynar Lighting Lithium polysilicate Lubricating oil Luminous paint Lupo/en Magnet coil insulation Magnetic material Makrolon Micatherm Microswitch Mineral oil Motor, electric Mylar Neoprene Nitrile-butadiene rubber Nomex Noryl Novolac Nylon Oil Optical fibre 0-ring Paint Paper Particle detector Pertinax Plexiglas Polyacrylate Polyamide Polybutylene terephthalate (PBTP) Polycarbonate Polychloroprene (Neoprene)

Polyester resin Polyethylene (PE) and (XLPE) Polyethylene terephthalate (PETP) Polyhydantoin Polyimide Polyolefin Polyphenylene oxide (P PO) Polyphenylene sulfide (PPS) Polypropylene (PP) Polysiloxane Polytetrafluoroethylene (Teflon PTFE) Polyurethane resin (PUR) Polyurethane rubber (PUR) Polyvinyl chloride (PVC) Polyvinyl toluene Quartz Relay Resin Resistofol Rubber Ry ton Scintillator Scotchcal Seal (0-ring) Silica Silicon detector Silicone oil Silicone rubber Sleeve Styrene-butadiene rubber (SBR) Switch Tape Teflon (PTFE) Tefzel Terminal board Textile Thermoplastic resin Thermosetting resin Thermoshrinking sheath Vacuum chamber tube Vacuum gasket Vacuum pump accessory Vacuum seal Vacuum valve Valvata Valve Vestolene Vi ton Wire Wood

15

Page 20: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Araldite Askarel Buna Dacron Dial a Dynel Epikote Flamtrol Furan Halar Hostalen Hypalon Hypermalloy Hytrel Kapton Kel-F Kevlar Kynar Lu pol en Makrolon Micatherm Mylar Neoprene Nomex Noryl Novolac Nylon Orlon Perbunan Pertinax Plexiglas Pyrofil Radox Resistofol Ryton Saran Scotch cal Teflon Tefzel Valvata Vestolene Vi ton

16

APPENDIX2

Explanation of trade names and popular names

Epoxy resin Oil, containing chlorinated diphenyls Synthetic rubber Polyethylene terephthalate Mineral oil Polyvinylidene chloride Epoxy resin Polyolefin, flame retardant Thermosetting resin Ethylene-chlorotrifluoroethylene Polyethylene Chlorosulfonated polyethylene Magnetic material Polyethylene terephthalate copolymer Polyimide Polychlorotrifluoroethylene Polyamide, aromatic Polyvinylidene fluoride Polyethylene and copolymers Polycarbonate Glass-mica composite Polyethylene therephthalate Polychloroprene rubber Aromatic polyamide Polyphenylene oxide Thermosetting resin Poly amide Polyacryl Acrylonitrile butadiene rubber Paper/phenolic resin Polyacryl Ethylene-propylene rubber (EPDM) Polyolefin Polyhydantoin Polyphenylene sulfide Polyvinylidene chloride Plastic display foil Polytetrafluoroethylene Ethylene-tetrafluoroethylene copolymer Mineral oil Polyethylene Fluorinated copolymer

Page 21: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX3

List of firms who collaborated in the irradiation tests presented in this volume

The firms listed below are those who participated in a collaboration to determine the radiation resistance of products offered to CERN. They supplied us with samples for testing or they supported our work by taking part in a discussion of the results.

In the alphabetical compilation of the catalogue are also quoted standard products, which have been taken from stock for radiation testing without contacting the firms. Therefore, for these entries, the supplier is not mentioned.

It is understood that better radiation-resistant materials may be found on the market or that the qualities of the tested materials have been upgraded since.

AEG, Allgemeine Elektrizitiits Gesellschaft -Telefunken, Ulm, Fed. Rep. Germany Angst & Pfister S.A., Geneva, Switzerland ASEA A/S, Allmiinna Svenska Electriska AB, Odense, Denmark Bachofen AG (repr. Burgess), Cheseaux, Switzerland BICC, British Insulated Callender's Cables Ltd., Wrexham, England Burgess, see Bachofen CEM, Cie Electro-Mecanique, see CERCEM CERCEM, Centre d'etudes et de recherches de la CEM, Lyon, France Chance-Pilkington, St. Asaph, Flintshire, Great Britain Ciba-Geigy AG, Basie, Switzerland CMC, Carl Maier Cie, Schaflhausen, Switzerland Dow Chemical Europe, S.A., Horgen, Switzerland Draka Kabel, Amsterdam, The Netherlands Egli, Fischer & Co. Ltd. (repr. T & B), Zurich, Switzerland Felten & Guillaume Kabelwerke, Cologne, Fed. Rep. Germany Gummi Maag AG, Diibendorf, Switzerland Hellermann, see Summerer, H.C. Heraeus Quarzschmelze, Hanau, Fed. Rep. Germany Huber & Suhner, Zurich, Switzerland ITT, Div. Diffusion Composants, Bagneux, France Joint Franiyais (Le), Bezons, France Labitzke Handels AG (repr. 3M Schweiz AG), Zurich, Switzerland Leybold Heraeus, Cologne, Fed. Rep. Germany Mader AG, Dr. W., Killwangen, Switzerland Precision Rubber, see Riibeli & Guigoz S.A. Raychem AG, Baar, Switzerland Rohm GmbH, Darmstadt, Fed. Rep. Germany Riibeli & Guigoz S.A. (repr. Precision Rubber), Ecublens, Switzerland Schott & Gen., Mainz, Fed. Rep. Germany Shell Switzerland, Zurich, Switzerland Sperry Vickers Lucifer S.A., Geneva, Switzerland Summerer, H.C. (repr. Hellermann), Zurich, Switzerland T & B, Thomas & Betts, see Egli, Fischer & Co 3M, Minnesota Mining & Manufacturing Co., see Labitzke Handels AG VAT, Vacuum-Apparate-Technik AG, Haag, Switzerland Walther Priizision, see Wieland & Oertli AG Wieland & Oertli AG, Illnau/Zurich, Switzerland

17

Page 22: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

ABS BBQ CSP CTFE EAR E-CTFE EP EPDM

EPN EPR ETFE ETP-Cu EVA FEP NBR OFHC-Cu PA PBTP PE PETP PMMA pp

PPO PPS PTFE PUR PVC SBR SIR XLPE

18

APPENDIX4

List of abbreviations used in this volume

Acrylonitrile-butadiene-styrene Benzimidazo-benzisoquinoline-7-one Chlorosulfonated polyethylene C hlorotrifl uoroeth y Jene Ethylene-acrylate rubber Ethylene-chlorotrifluoroethylene Epoxy resin Ethylene-propylene difunctional monomer copolymer, e.g. Ethylene-propylene diene rubber Epoxy-phenol-Novolac resin Ethylene-propylene rubber Ethylene-tetrafluoroethylene Electrolytic tough-pitch copper Ethylene vinyl acetate Perfluoroethylene-propylene Nitrile-butadiene rubber Oxygen-free, high-conductivity copper Poly amide Polybutylene terephthalate Polyethylene Polyethylene terephthalate Polymethyl methacrylate Polypropylene Polyphenylene oxide Polyphenylene sulfide Polytetrafluoroethylene, Teflon Polyurethane rubber Polyvinyl chloride Styrene-butadiene rubber Silicone rubber Polyethylene, cross-linked

Page 23: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX 5

Tables of general relative radiation effects

There are tables for the following categories of items:

5.1 Cable insulations

5.2 Elastomers

5.3 G-values

5.4 Hoses

5.5 Oils

5.6 Paints

5.7 Textiles

5.8 Thermoplastic resins

5.9 Thermosetting resins

These tables are modified versions of those given in the respective references. Cross-references to these tables are contained in the alphabetical data compilation section. An alphabetical index of the contents follows.

19

Page 24: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

List of all materials presented in this part in tables of beneral relative radiation effects

Acetate Acetone Acrylic rubber Acrylonitrile rubber Acrylonitrile-butadiene rubber Acrylonitrile-butadiene-styrene (ABS) Aniline-formaldehyde Aromatic alkyl Aromatic polyamide Benzene Bromoform Butyl rubber Carbon tetrachloride Cellulose esters Cellulose acetate Cellulose fibre Chlorinated rubber C hlorobenzene Chlorofluorocarbon oil Chloroform Chlorosulfonated polyethylene (CSP) Cotton Dacron Dichloroethane Dichlorobenzene Dyne! Epoxy resin Esters Ethers Ethyl bromide Ethylene-chlorotrifluoroethylene (E-CTFE) Ethylene-propylene polyallomer Ethylene-propylene rubber (EPR) Ethylene-tetrafluoroethylene (ETFE) Ethylene vinyl acetate (EV A) Flamtrol Fluorinated compounds Halar Hypalon Hytrel Kapton Kel-F Melamine-formaldehyde Mineral oils Mylar Neoprene Nomex Nylon Orlon

20

Perbunan Perfluoro~thylene-propylene (FEP) Phenolic resin Phosphate oil Polyacryl Polyacrylonitrile Polyamide (Nylon) Polybutadiene Polycarbonate Polychloroprene rubber (Neoprene) Polychlorotrifluoroethylene (Kel-F) Polyester Polyethylene (PE) Polyethylene cross-linked (XLPE) Polyethylene terephthalate (PETP) Polyglycol oil Polyimide Polyisobutylene Polymethyl methacrylate (PMMA) Poly olefin Polyphenylene oxide (PPO) Polypropylene (PP) Polysilox:me (Silicone rubber SIR) Polystyrene Polytetrafluoroethylene (Teflon PTFE) Polyurethane resin (PUR) Polyurethane rubber (PUR) Polyvinyl alcohol Polyvinyl butyral Polyvinyl chloride (PVC) Polyvinyl formal Polyvinylidene chloride Pyrofil Radox Rayon Saran Silicate oil Silicone oil Silicone resin Silicone rubber (SIR) Silk Styrene Styrene-butadiene rubber (SBR) Teflon PTFE Tefzel Urea-formaldehyde Vinyl chloride polymers Wool

Page 25: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX 5.1

General relative radiation effects: Cable insulation

These appreciations are taken from the references cited and can only serve as a general guideline. Atmospheric and other environmental conditions such as temperature and dose rate

are not taken into consideration. See also Sections 2 and 3.

Polyimide (Kapton)

Polyurethane rubber (PUR)

Ethylene-propylene rubber (EPR/EPDM)

!:::::::::::·:::···.·.·.·.·.·.·.·.·.·.·.·:::::::::::::::::::::;::::::::::::::::<:::::::::::::Bl

C: :: :: > .. ::; :::::: ::: ::::::::::;:;:::::::::::::::.::::::; ::Jl$llll~I t::::::::::::::::::::::::::::::::;:.·:·::::::::;:;:;::::.;:::;::.:::::11::01§$~1t-il::i

Polyethykne/Polyolefin (e.g. PE/PP, XLPE)

Chlorosulfonated polyethylene (Hypalon)

Ethylene-chlorotrifluoroethylene (Halar) l: ·:;: ·:; :; : ; : ; : : : ; : : ;: ; : ; : ; : : ·:::::: ;: : . : : : : : : : : : : : : : : : : ; : : : : ti~~:8;:-::;:::;:§'a::>t.;!§

Ethylene-propylene rubber (EPDM) flame ret. (Pyrofil) [:::::·:::::::::::::::::::::::::::::::::::;:'.:::::;:;:;:::;:;::-

Ethylene-tetrafluoroethylene copolymer (Tefzel) !::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::~

Ethylene vinyl acetate(EVA) j:::<<:::· "-:>. · · .. :;::::::<:::;<:;:::;:;:;<:;:;:;-

Polychloroprenerubber(Neoprene) j:;:;:;:;:;:::;:::::;:::::::::::::::::::::::::::::::::::::::::::~#:j

Polyethylene terephthalate copolymer (Hytrel) (::::: : :;::::::::<:>::::::::: :::::_:::<<:>::::::::::>;:

Polyolefin,flame-retardant(Flamtrol,Radox) (:::::: :::::::::::::::::::::::::::::::::::::::::::::>:::::::-

Polyvinylchloride (PVC) (::::; :; : : : : : : <: :; : : : : : : : : : : : : : : : :: : : : : : : : : : ; : : : : :; :; : : : ; : ; : ·

Siliconerubber(SIR) [; ;;:; ;;::; : ;:::: ::::::::::::N.m;:;~

But y I rubber [..,<..-.: :.: : .... : : ..;..;.;.;....;....;..~.-. .... """'o;m;a:u;;oi;;u;u;io:u;;o ..... a.u;&LJLU..LL.1....,.U&.11

Perfluoroethylene-propylene (FEP) !:::'.:'.:'.:'.:;:::::.:;:::;:::::;~

Polytetrafluoroethylene (Teflon PTFE)

REFERENCES: l

DOSE IN GRAY

DOSE IN RAD

USEFUL RANGE

USE NOT RECOMMENDED

JO' !Ol

J04

106

!Ol

JO'

106

108

107

109

108

JO'"

21

Page 26: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX 5.2

General relative radiation effects: Elastomer

These appreciations are taken from the references cited and can only serve as a general guideline. Atmospheric and other environmental conditions such as temperature and dose rate

are not taken into consideration. See also Sections 2 and 3.

Polyurethane rubber (PUR) f: ..

Ethylene-propylene rubber (EPR)

Styrene-butadiene rubber (SBR) I: ... ::::::::::::~<mt

Polychloroprene rubber (Neoprene) !::: ..... . .·.·.·.··::::.·:~-

Chlorosulfonatedpolyethylene(Hypalon) (:::: .. :::::'.~$

Acrylonitrilerubber [:;:::::::::::::;:::;:::::::::::;;::::;:::::~ a Acrylic rubber f::::::::::::::::::::::::::::::::::::-

Siliconerubber(SIR) !:::::::::::::::::::::::::::::::::::::::-

Fluororubber j:::::::::::::::::<:::::::::::::::>::~

Butylrubber C::;:;:;::::: :~~

104 105 106 JO'

Gamma dose. Gy

Damage Utility

Incipient to mild Nearly always usable Mild to moderate Often satisfactory Moderate to severe Not recommended

REFERENCES: 36

22

Page 27: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX 5.3

General relative radiation effects: G-value

These values are taken from the references cited and can only serve as a general guideline. Atmospheric and other environmental conditions such as temperature and dose rate

are not taken into consideration. See also Sections 2 and 3.

Compound G-value*)

Benzene : '--=-\ 1.8

Styrene: -CH= CH2 1.6

Chlorobenzene: 17.3

o-Dichlorobenzene: 30.0

Acetone: CH3 - CO - CH3 50.0

Ethyl bromide: CH3 - CH2Br 28.0

1,2-Dichloroethane: CH2Cl - CH2Cl 41.0

Chloroform: CHCl3 59.5

Bromoform: CHBr3 57.0

Carbon tetrachloride: CC14 70.0

*) G-value = number of product molecules formed or reactant molecules consumed per 100 eV of energy absorbed by the compound. The G-value quoted here is for the production of free radicals.

REFERENCES: 36, see also 43

23

Page 28: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX 5.3

General relative radiation effects: G-value of polymers

These values are taken from the references cited and can only serve as a general guideline. Atmospheric and other environmental conditions such as temperature and dose rate

are not taken into consideration. See also Sections 2 and 3.

Polymer

Polyethylene (PE) Polystyrene Polyacrylonitrile

Polyvinyl chloride (PVC) Polyvinyl alcohol Polybutadiene Polymethyl methacrylate (PMMA)

Polyisobutylene

Polytetrafluoroethylene (Teflon PTFE) Polyethylene terephthalate (PETP, Mylar) Polyamide (Nylon) Styrene butatiene rubber (SBR) Polyurethane rubber (PUR) Polysiloxane Polychloroprene (Neoprene)

G-value*)

2.1 0.03 0.4

0.3 1.7

0.2 1.3

0.87

0.03 0.15 I.I 0.15 0.7 0.6 0.1

Composition

H2(95.5%); C 3Hg(3.4%) H2( 100%) H2(24%); NHi8%); C2N 2(67.5%) HCl H2(95%); C0(4.3%) H2 + CH4(100%) Hz( 18%); CHi 15%); C0(36%); COz(25%); C 3H 8(5.3%) H 2 + CHi95.5%) C02 + C 3H 8(4.5o/o) CO+ C02

*) G-value = number of product molecules formed or reactant molecules consumed per I 00 eV of energy absorbed by the polymer. The G-value quoted here is for the production of all gases listed.

REFERENCES: 36, see also 43

24

Page 29: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX 5.4

General relative radiation effects: Hoses

These appreciations are taken from the references cited and can only serve as a general guideline. Atmospheric and other environmental conditions such as temperature and dose rate

are not taken into consideration. See also Sections 2 and 3.

A. Plastics

Polyphenylene oxide (PPO) [::::: . . .. ...... . ::::::::::::::::::::::::::::::::::::::::::::::::: .. Polyolefins, glass reinforcement

Polyethylene (PE)+ SR I: .. ::::::::::::::::~

Combination PE-PVC ··.·.·.·.·.··:::~

Polyvinyl chloride (PVC)+ SR* 1 1: .. ............. :~

Polyamide(Nylon) (::: ...

Polytetrafluoroethylene (Teflon PTFE)

Polytetrafluoroethylene (Teflon PTFE) **1 ..

B. Elastomers

Acrylonitrile-butadiene rubber (Perbunan) +SR !::::::<:::::::::::::::::::::::::::::::::~

Polychloroprene(Neoprene) +SR !::::::::::::::::::::::::::::::::::::::::::-

Silicone rubber + SR

Butyl rubber + SR

103 104 10' 10' 108

Gamma dose, Gy

SR = synthetic reinforcement. All results for l bar, except*) for I and for 15 bar and**) for 20 bar water bursting pressure.

REFERENCES: 36

Damage

Incipient to mild Mild to moderate Moderate to severe

Utility

Nearly always usable Often satisfactory Not recommended

25

Page 30: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX 5.5

General relative radiation effects: Oil

These appreciations are taken from the references cited and can only serve as a general guideline. Atmospheric and other environmental conditions such as temperature and dose rate

are not taken into consideration. See also Sections 2 and 3.

Aromatic alkyl

Ethers

Mineral oils

Esters

Polyglycols

Silicones

Silicates

Phosphates

Chlorofluorocarbons

Fluorinated compounds

k: ..... f:::::::::::::::::::::::::::::::::::::::::::::::::~

!:>::::::>::::::::::::::>::::::::::~

(:::::::::::::::::::::-

!:::;:::;:;:;:;:~

Hf JO' 106 JO' 108

Gamma dose, Gy, in oxygen-free atmospheres

Damage Utility

Incipient to mild Nearly always usable Mild to moderate Often satisfactory Moderate to severe Not recommended

REFERENCES: 36

26

Page 31: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX 5.6

General relative radiation effects: Paint

These appreciations are taken from the references cited and can only serve as a general guideline. Atmospheric and other environmental conditions such as temperature and dose rate

are not taken into consideration. See also Sections 2 and 3.

Epoxy resins

Phenolics

Melamine-formaldehyde

Polyurethanes

Polyesters

Vinylchloride polymers

Silicone resins

Chlorosulphonated polyethylene

...... ' . . . . . . . . . ' ..... ' :::::::::·~

::::::::::~

!::::::::::::::::::::::::: ·.·.::::::::::::::::::~

!:::::::::::::::::::::::::::::::::::~

!:::::::::::::::::::::::::::::::::::::::::~

!:::::::::::::::::::'.:::::::::::::::.&..~

Polychloroprene rubber (Neoprene) f::::::::::::::'.:::;:;:;:;:;:;:;:;:~

Chlorinated rubber

Polymethyl methacrylate

Cellulose esters

REFERENCES: 36, see also 28

104

Gamma dose, Gy

Damage

Incipient to mild Mild to moderate Moderate to severe

107 108

Utility

Nearly always usable Often satisfactory Not recommended

27

Page 32: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX 5. 7

General relative radiation effects: Textile

The~e appreciations are taken from the references cited and can only serve as a general guideline. Atmospheric and other environmental conditions such as temperature and dose rate

are not taken into consideration. See also Sections 2 and 3.

A. Natural fibres

Wool

Acetate

Silk

Cellulose fibre (Rayon)

Cotton

8. Synthetic fibres

Aromatic polyamide (Nomex)

Polyester (Dacron)

Polyacryl (Orlon)

Polyvinylidene chloride (Saran. Dyne!)

Poly amide (Nylon)

1::::::::•:::::::·~~$!1

(:::::::::•:-

i::::::::::::::::::•:•:::::::::-11

104 10~

Gamma dose, Gy

Damage

Incipient to mild Mild to moderate Moderate to severe

106 107

Utility

Nearly always usable Often satisfactory Not recommended

108

REFERENCES: 36

28

Page 33: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX 5.8

General relative radiation effects: Thermoplastic resin

These appreciations are taken from the references cited and can only serve as a general guideline. Atmospheric and other environmental conditions such as temperature and dose rate

are not taken into consideration. See also Sections 2 and 3.

Polystyrene

Acrylonitrile-butadiene-styrene (ABS)

Polyvinyl chloride (PVC)

Polyethylene (PE)

Polyvinyl formal

Polycarbonate

Ethylene-propylene polyallomer

Polyvinylidene chloride

Polychlorotrifluoroethy lene (Kel-F)

Polyvinyl butyral

Cellulose acetate

Polypropylene

Polymethyl methacrylate

Polyamide(Nylon)

Perfluoroethylene-propylene (FEP}

Teflon PTFE and FEP (Vacuum)

Polytetrafluoroethylene (Teflon PTFE)

REFERENCES: 36, 37, 43

f::::::: ............. .

L .·.·.·.·.·.·.·.·.·.·. .·.·.·.·.·.·.· .. · .. ·.·.·.· ... ' .. :::::

... ·.·.·.·.·.·.·.·.·. ....... :~ I:: .....

t: ... . . . . . . . . ::::::::-

.... :::::::::~

:::::::::::-

I> ..... ::::::::::::::::-

f .......... .

(::::::: ...

j::::::

.. ::::~

:::::;:~ _ .. :;::::::::~:::::::~::::::::::::::::. (:::::::::::::::::::::::::::::::::~

(:::-:;:.·::-:::::::::::::::::::::::::::::::::::~

[:::::::::::::::::::::::::::::::::::::::::::::::Wj

!::::::::::::::::::::::::::::::::::::::::::::::::;:::~

102 103 104

Gamma dose. Gy

Damage

f-.· .·.·.·.·.:) Incipient to mild

~~~ Mild to moderate U Q I Moderate to severe

106

Utility

Nearly always usable Often satisfactory Not recommended

107 108

29

Page 34: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX 5.9

General relative radiation effects: Thermosetting resin

These appreciations are taken from the references cited and can only serve as a general guideline. Atmospheric and other environmental conditions such as temperature and dose rate

are not taken into consideration. See also Sections 2 and 3.

Phenolic, glass laminate !:: ..... .

Phenolic, mineral filled I: .. :::::: :>:::<: <<::::::::<::::::::;>:::;:;:::::;:;:;:;:;:;:::::;:;:;:;:;:;:;:;:;:;:;~

Phenolic, unfilled (:>: ::::>>::>>:::::;:~

Epoxy, glass laminate l::::::<:::::::::::::::::::::>::::::::::::::::>::::>:::::::::::·:::::::::::::::::::::::::::::::::::J

Epoxy, aromatic-type curing agent (:;:;:;:;:;:::;:;::::::::::::::::::::::::::::::::>::::::::::::::::::::::::::::::::~

Polyurethane(PUR) !::::::::::::::::::::::::::::'.:::::::::::::::::::::::::::::::::::::::<::::::::::::::::~

Polyester, glass filled !::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::~

Polyester, mineral filled [:;:;:;:;:;:;:;:::::;:::;:::;:;:::;:;:::>:::::;:::::::'.:~

Polyester, unfilled !::::<:;:'.: :>>:~

Polyethylene terephthalate (Mylar) !<:::::::::::::· :::::::::::::::~

Silicone, glass-filled !:::::::::::::::::::::<:::::::::::::::::>:::::::::::::::::::::::::<:::::::::::::::~

Silicone, mineral-filled !:::::::::::::::::::::::::::::::::::::::::::::::::::>:::::::::::::::::::::::::::::<:~

Silicone, unfilled E:'.:'.:'.:'.:'.:'.:>>::::'.:::>:::::<::<::::::<:::::>::::::::::~llijijilm

Melamine-formaldehyde f :::::::::::::::::::::::::::<::::::~

Urea-formaldehyde (:::::>::::::::::::::::::::~

Aniline-formaldehyde -~::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::

10• 101

Gamma dose, Gy

Damage

Incipient to mild Mild to moderate Moderate to severe

106 107

Utility

Nearly always usable Often satisfactory Not recommended

1()8

REFERENCES : 36, 3 7, 43

30

Page 35: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX6

Classification of materials and components contained in this volume according to the dose range up to which they may typically be used.

Materials Upper dose limit Materials in Gy = 100 rad

Acrylic scintillator 10 2- 104 Araldite B (epoxy resin)

Butyl rubber 5 x 104

Electronics components (active) 102- 103

Araldite F (epoxy resin) Epikote(epoxy resin)

Optical fibre 10-102 Epoxy Novolac Perfluoro ethylene-propylene Epoxy resin, aromatic hardener (FEP) 5 x 104 Glass-fibre reinforced EPR-hoses

Phenolic resin, unfilled 104

• Polyacryl (Plexiglas) JO' > Mineral oil Paints based on epoxy or

Polyamide (Nylon) IX JO' polyurethane resins Polyester resin, unfilled 5 x 104 Polyimide resin Silicone oil 5 X 10' Special radiation resistant Silicone rubber 5 X 10' lubricants Teflon (PTFE) 103 Special radiation resistant motors Viton 1-2 X JO'

Araldite D (epoxy resin, cured at Cerium-doped glass ambient temperature) Ryton (PPS)

Chlorosulfonated PE Inorganic filled resins: (Hypalon, CSP) - Epoxy, aromatic hardener

Cross-linked PE (XLPE) - Phenolic Ethylene-acrylate rubber (EAR) - Polyester Ethylene-propylene rubber (EPR) - Polyimide Ethylene vinyl acetate (EV A) - Polyurethane Flamtrol (polyolefin) 1-2 x 106 - Silicone Halar(CTFE) Hytrel (PETP copolymer) Aluminium oxide Lupolen (PE) Magnesium oxide Polychloroprene (Neoprene) Magnetic materials Polyolefin Metals Polyvinyl chloride (PVC) Mica

Glass fibre Quartz

•) Use of these materials in radiation areas is not recommended or to be used with precautions.

Upper dose limit in Gy = 100 rad

1-2 x 107

IX 108

> 108

31

Page 36: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

APPENDIX 7

Detailed description of data entry sheets

The data entry sheets are designed to provide the maximum information for a given item, as far as this is available, with only the minimum use of abbreviations and symbols, and to be largely self-explanatory (see also Section 3 of the text). In the following list, some indi­cations are given regarding the layout of the different

entries, especially to help understand small differences in ~he presentation of the data. The list of comments below refers to the corresponding circled numbers on the sample data sheet reproduced on the opposite page. It should be understood that all indications mentioned in these comments are subject to exceptions, especially in cases where the appropriate information was not avail­able.

l The alphabetic position of the keyword.

2 The keyword grouping a class of items by their usual application. This does not mean that all items under one keyword are equivalent for a given application, but that they share a characteristic property.

3 The dominant component among the base materials, or the most radiation-sensitive component. In the case of composite materials, more than one material is some­times given. See 7 for a complete description of the base materials composing the tested item.

4 The type identification of the material as given by the supplier. In some cases the trade name of a characteris­tic material component is added after a semicolon. A dash indicates that the supplier was not contacted.

5 The name, given in a shortened/arm (see Appendix 3 for more details), is normally that of the supplier of the finished, tested product. However, it should be noted that this supplier is not always the same as the firm produc­ing the base products. A dash indicates that the supplier was not contacted. See also 7.

6 Identification number given by the authors to the tested materials. The integer part of the first number represents the identification of a group of items, which have been tested by the same method, or which simply belong to a group of different items used together in an apparatus. The fractional part identifies the single item described. The year whe:1 the test was carried out is added as gene­ral information.

7 A description of the item and its intended application, together with details of composition as far as is known. Trade names of materials are added in brackets in some cases.

8 Application at CERN: if known to us, details are given here. If an application was only proposed but not real­ized, this is mentioned under 7.

9 Irradiation conditions. In case of reactor irradiation. the exact irradiation position together with the approximate gamma dose rate is given. More details can be found in Table I and Ref. 7. The contribution to the dose by other components of the complex reactor irradiation is usually less than 5%. However. if the materials are especially sensitive to particle irradiation. as with crystals or metals. the fluence of fast neutrons is given instead of the dose. For the accelerator irradiations, the position

32

APPENDICE 7

Description detaillee des feuilles de donnees

Les feuilles de donnees ont ete preparees de fac;on qu'un maximum d'informations, dans la mesure ou elles

sont disponibles, soient presentees en utilisant un mini­mum de symboles et d'abreviations. et que ceux-ci

soient suffisamment clairs (voir aussi la section 3 du texte). Quelques indications sont donnees dans la liste suivante, concernant le schema des pages de donnees pour les divers materiaux, pour faciliter en particulier !'interpretation des petites differences dans la presenta­tion des donnees sur des materiaux comparables. Cette liste fait reference aux numeros entoures d'un cercle sur la feuille de donnees servant d'exemple a la page ci-contre. 11 va sans dire que toutes !es indications don­nees ici souffrent des exceptions, surtout si !'informa­tion appropriee n'a pas ete disponible.

I Position du mot-cle dans /'alphabet.

2 Mot-cle pour un ensemble de materiaux groupes par application. Ceci ne signifie pas que tous Jes materiaux soient equivalents pour une application donnee, mais qu'ils ont en commun une propriete caracteristique.

3 Composition des matieres de base ou composant le plus sensible aux radiations. Pour les materiaux composes, plusieurs matieres sont parfois citees. Voir sous 7 la liste complete des matieres de base qui constituent le materiau examine.

4 Denomination du type, donnee par le fournisseur de ce materiau. Dans quelques cas, le nom de marque d'une matiere caracteristique est ajoute apres un point-virgule. Un tiret signifie que le fournisseur n'a pas ete contacte.

5 L 'abreviation du nom dufournisseur (voi1 Appendice 3 pour le detail), qui est normalement le fournisseur du produit final teste. A noter que ce fournisseur n'est pas toujours celui qui a fourni les produits de base. Un tiret signifie que le fournisseur n'a pas ete contacte. Voir aussi 7.

6 Numero d'identification des materiaux testes, donne par les auteurs. La partie entiere du premier nombre repre­sente !'identification d'un groupe de materiaux qui soil ont ete testes d'apres la meme methode, soil constituent un groupe de materiaux divers utilises pour le meme appareillage. La partie fractionnelle donne !'identifica­tion de la piece concernee. L'annee pendant laquelle l'es­sai a ete effectue est rajoutee pour information.

7 Description de l'objet, et son application prevue. Elles sont donnees ensemble, avec le detail de la composition de l'objet, si elle est connue. Le nom de marque est rajou­te dans certains cas entre parentheses.

8 Application au CERN: si nous la connaissons. les details en sont donnes ici. Si une application a ete propo­see mais pas realisee ceci sera mentionne sous 7.

9 Conditions d'irradiation. Dans le cas d'une irradiation dans le reacteur nucleaire, la position exacte de l'irradia­tion est donnee, avec le debit de dose gamma approxi­matif. Pour plus de details, voir tableau 1 et ref. 7. La contribution a la dose par d'autres composants du champ de rayonnemer.t dans le reacteur est en general en dessous de 5%. Toutefois si !es materiaux sont speciale­ment sensibles a !'irradiation par des particules, comme

Page 37: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

A ADHESIVE TAPE BASE MATERIAL: Polyamide/mica/paper. rubber adhesive

TYPE: 6610;Nomex ® SUPPLIER: CMC

IDENTIFICATION: 102.5-1974

f/f(O)

1%1

100

50

IO'

® SYMBOL

________ _l

IO' IO' DoselGyJ

@ PROPERTY INITIAL VALUES

force to take off 4.3 N/25 mm

®

IO'

ACD ADHESIVE TAPE 0

BASE MATERIAL: Polyamide/mica/paper, rubber adhesive

TYPE: 6610; Nomex

SUPPLIER: CMC

IDENTIFICATION: I02.5-I974

DESCRIPTION OF MATERIAL: Self-adhesive film for insulation purposes. Film material: polyamide reinforced paper with mica (Nomex). Adhesive: synthetic rubber. thermosetting.

© APPLICATION AT CERN:

® IRRADIATION CONDITIONS:

Type: Reactor ASTRA. position EI in air, dose rate 30 Gy/s Doses: 5 X IO', IX 106

, 5 X I06, IX IO' Gy

® METHODS OF TESTING: Pieces of film (I IS X 25 mm), stuck to ~n aluminium support of the same dimensions without heat treat­ment, were irradiated, after which the film was peeled off at a constant rate of 50 mm/min. The bending radius was fixed by a roller of IO mm diameter and the mean force measured by a tensile testing machine.

®RESULTS: Before irradiation, the peeling-off force was 4.3 N for a width of25 mm. After irradiation, the force decreased but remained effective up to 5 X I 06 Gy. At I X I 01 Gy, the rubber no longer stuck to the film; instead, it adhered to the metal. The colour darkened with the dose.

Remarks:

® REFERENCES: I8

®APPRECIATION: See Appendix 7

® ®® ,~-,----~--.--~~n~ote~stl~lllllll-

IO' IO' 101 IO' IO' IO' IO' 108

Dose (Gy)-+

Page 38: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

code refers to Table 1, where the characteristics of the radiation field are given; in most cases the dose as measured with our dosimeters will be sufficient for the interpretation of data.

10 The methods of testing are described. If no number of a standard covering this test is given, this means that we modified a standard test to fit our needs (see point 12 for more details). When comparing the test results of simi­lar items, it is important that the integer part of the iden­tification number (see 6) be the same, otherwise the test­ing method may have been different.

11 The results obtained are briefly described, bearing in mind the methods of testing 10 and the irradiation con­ditions and doses 9. In some cases, a cross-reference is cited under "Remarks", where data relating to similar materials can be found. This information together with the test results was used for the appreciation 13.

12 The number(s) given refer(s) to the list of references at the end of the introductory text (page 8).

13 In this appreciation, we give warning if the material is especially radiation sensitive, and show a scale where the ranges of different degrees of degradation are marked: blank-"no damage"; hatched 14-"moderate damage"; black 15 - "severe damage". If in the range considered the material is probably susceptible to damage but no test was performed, this region is marked "no test" 16. If the appreciation refers to standard mechanical properties, thi5 is stated explicitly, in which case the beginning of 14 marks a change of 25% and of 15 of 50% of the most sensitive property (tlexion test: flexural strength, tensile tests: elongation at break). Otherwise we judged the test results in relation to the intended application.

17 If the test results justify a representation in a graph, or if other additional information is given, there will be a repetition of positions I to 6 on the left-hand page. Otherwise, this page is left blank.

18 If there is a graph of irradiation test results, please pay attention to the scales. The abscissa may be linear or logarithmic, and the numbers on the ordinate, which nor­mally are percentage values normalized to the unirra­diated value given under 20, may sometimes give a loga­rithmic measure of this value (see 19). The graph can also be replaced by a table.

19 Identification of plotted symbols and measured func­tions. The initial values are given, and sometimes an indication of the estimated error of measurement, if available. The lines are intended only as a guide to the eye. If one of the symbols relates to a special interpreta­tion of the scale, this is stated.

34

par exemple les cristaux ou Jes metaux, la fluence de neu­trons est donnee au lieu de la dose absorbee. Pour les irradiations dans Jes accelerateurs, le code de position se refrre au tableau I, ou la caracteristique du champ de rayonnement est donnee: dans la plupart des cas, la lec­ture des mesures de nos dosimetres sera suffisante pour !'interpretation des donnees.

IO i'v!ethodes d'essais. Si l'on ne donne pas de numero de norme pour un essai, cela signifie que Jes normes ont ete modifiees pour satisfaire nos besoins ( voir point 12 pour plus de details). Si l'on compare les resultats d'essais de produits similaires. ii est important de verifier que le numero d'identification (voir 6) est le meme, sinon la methode d'essai a pu etre differente.

11 Les resultats obtenus sont brievement decrits en tenant compte de la methode utilisee pour Jes essais (voir 10) et des conditions d'irradiation et des doses (voir 9). Dans certains cas, une reference est citee sous "Remarks", ou des resultats similaires peuvent etre trouves. Cette infor­mation a ete utilisee, avec les resultats de nos essais, pour I' appreciation donnee sous 13.

12 Le(s) numeros(s) renvoie(nt) a la liste de references don­nee a la fin du texte d'introduction (voir page 8).

13 Dans cette appreciation, nous donnons un avertisse­ment si le materiau est particulierement sensible aux rayonnements; nous montrons une echelle ou les diffe­rents degres de degradation sont indiques: blanc-"pas de dommage"; hachure 14 -"dommage leger"; noir 15 -"dommage severe". Si dans la gamme consideree le materiau est susceptible d'etre endommage mais qu'au­cun essai n'a ete effectue, cette region 16 sera marquee "no test" (pas d'essais). Dans le cas ou I' appreciation se refrre aux essais mecaniques standard, ceci sera men­tionne explicitement; dans ce cas, le debut de 14 indique un changement de 25% et le debut de 15 un changement de 50% de la propriete la plus sensible (essais de tlexion: resistance a la tlexion; essais de traction: allongement a la rupture). Dans Jes autres cas, nous avons juge Jes re­sultats d'essais en relation avec )'application prevue.

17 Dans le cas OU Jes resultats d'essais justifient la presen­tation d'un graphique ou d'une information comptemen­taire, Jes positions I a 6 seront reproduites sur la page opposee. Dans le cas contraire, cette page restera blanc he.

18 Dans le cas OU ii y a un graphique des resultats d'irra­diation, veuillez tenir compte des echelles: Jes abscisses peuvent etre lineaires OU logarithmiques. Pour l'ordon­nee, nous donnons en general les valeurs en pourcentage de degradation, normalisees a la valeur "non irradie" donnee sous 20. Dans certains cas, l'ordonnee peut aussi representer la degradation des proprietes mesu­rees sur echelle logarithmique (voir 19).

19 Identification des symboles utilises dans le graphique et des proprietes mesurees. On donne la valeur initiale, et quelquefois l'erreur de mesure estimee, si disponible. Les lignes qui relient les points de mesure sont le plus souvent tracees simplement comme guide. Dans le cas OU l'un des symboles se refrre a une interpretation Spe­ciale de l'echelle, ceci est mentionne ici.

Page 39: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

ALPHABETICAL COMPILATION OF DA TA

Acrylic resin see Paint see Scintillator

Acrylonitrile-butadiene rubber (NBR) see Seal

ADHESIVE TAPE Plastic display foil

Entries and cross-references

Polyamide/mica paper, rubber adhesive Polyamide paper, rubber adhesive Polyethylene terephthalate (PETP), rubber adhesive Polyhydantoin, resin adhesive Polyimide, resin adhesive see also Insulating tape

Aluminium oxide see Ceramic

Araldite, trade name of Ciba-Geigy Epoxy resin, see Thermosetting resin

Asbestos cement see Ceramic

Askarel Chlorinated oil, see Insulating oil

A

35

Page 40: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Materials listed in General Tables in Appendix 5

Acetate see Textile, p. 28

Acetone see G-value, p. 23

Acrylic rubber see Elastomer, p. 22

Acrylonitrile rubber see Elastomer, p. 22

Acrylonitrile-butadiene rubber see Hose, p. 25

Acrylonitrile-butadiene-styrene (ABS) see Thermoplastic resin, p. 29

Alkyl aromatics see Oil, p. 26

Aniline-formaldehyde see Thermosetting resin, p. 30

Aromatic polyamide see Textile, p. 28

A

37

Page 41: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

A ADHESIVE TAPE

BASE MATERIAL: Plastic display foil

TYPE: Scotchcal

SUPPLIER: Labitzke

IDENTIFICATION: 104-1975

DESCRIPTION OF MATERIAL: Self-adhesive warning sign with black letters on a yellow background, dimensions 300 X 100 mm2

, made of Scotch cal

APPLICATION AT CERN: Warning signs used for various purposes in radiation areas

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 5 X 105

, I X 106, 5 X 106 Gy

METHODS OF TESTING: Samples of dimensions 115 X 20 mm2

, stuck to an aluminium sheet, were irradiated and afterwards examined qualitatively.

RESULTS: At 5 X 105 Gy, no changes were observed. At 106 Gy, the yellow background coloration became greenish. No change in contrast or adhesion. At 5 X 106 Gy, the background coloration was greenish, bubbles of 5-10 mm diameter had formed between the plastic foil and the support, and it was easy to scratch off the foil. Corrosion of the aluminium support began under the bubbles.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

1111111111111

106

Dose (Gy)-+

39

Page 42: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

A ADHESIVE TAPE BASE MATERIAL: Poly amide/mica paper, rubber adhesive

TYPE: 6610; Nomex

SUPPLIER: CMC

IDENTIFICATION: 102.5-1974

100

f/f(O) [%)

50

0'--~--"~~~--'-~~--'~~--'-~~~~~~--'-~~~~~~~~~--

40

104

SYMBOL

• PROPERTY

force to take off

Dose[Gy)

INITIAL VALVES

4.3 N/25 mm

Page 43: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

A ADHESIVE TAPE

BASE MATERIAL: Polyamide/mka paper, rubber adhesive

TYPE: 6610; Nomex

SUPPLIER: CMC

IDENTIFICATION: 102.5-1974

DESCRIPTION OF MATERIAL: Self-adhesive film for insulation purposes. Film material: aromatic poly amide paper with mica (Nomex). Adhesive: synthetic rubber, thermosetting.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 5 X 105

, 1 X 106, 5 X 106

, 1 X 107 Gy

METHODS OF TESTING: Pieces of film (115 X 25 mm), stuck to an aluminium support of the same dimensions without heat treat­ment, were irradiated, after which the film was peeled off at a constant rate of 50 mm/min. The bending radius was fixed by a roller of 10 mm diameter and the mean force measured by a tensile testing machine.

RESULTS: Before irradiation, the peeling-off force was 4.3 N for a width of 25 mm. After irradiation, the force decreased but remained effective up to 5 X 106 Gy. At 1 X 107 Gy, the rubber no longer stuck to the film; instead, it adhered to the metal. The colour darkened with the dose.

Remarks:

REFERENCES: 18

APPRECIATION: See Appendix 7

1111111

103 106

Dose (Gy)-+

41

Page 44: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

A ADHESIVE TAPE BASE MATERIAL: Poly amide paper, rubber adhesive

TYPE: 6510; Nomex

SUPPLIER: CMC

IDENTIFICATION: 102.6-1974

100

f/f(O) [%]

50

O'--~~J..._~~~J..._~~--'-~~-"-~~~--'-~~-'----~~--'-~~-~--'-~~-w

42

104

SYMBOL

• PROPERTY

force to take off

Dose[Gyl

INITIAL VALUES

23 N/25 mm

Page 45: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

A ADHESIVE TAPE

BASE MATERIAL: Polyamide paper, rubber adhesive

TYPE: 651 O; Nomex

SUPPLIER: CMC

IDENTIFICATION: 102.6-1974

DESCRIPTION OF MATERIAL: Self-adhesive film for insulation purposes. Film material: aromatic polyamide paper (Nomex). Adhesive: synthetic rubber, thermosetting.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy Is Doses: 5 X 105, 1 X 106

, 5 X 106, 1 X 107 Gy

METHODS OF TESTING: Pieces of film (115 X 25 mm), stuck to an aluminium support of the same dimensions without heat treat­ment, were irradiated, after which the film was peeled off at a constant rate of 50 mm/min. The bending radius was fixed by a roller of 10 mm diameter and the mean force measured by a tensile testing machine.

RESULTS: Before irradiation, the peeling-off force was 23 N for a width of 25 mm. After irradiation, the force remained comparatively high up to 5 X 106Gy (23%), but at 107 Gy the gum no longer stuck to the metal. The colour darkened with the dose.

Remarks:

REFERENCES: 18

APPRECIATION: See Appendix 7

111111111

104 106 107

Dose (Gy)-+

43

Page 46: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

A ADHESIVE TAPE BASE MATERIAL: Polyethylene terephthalate (PETP), rubber adhesive

TYPE: 1050; Mylar

SUPPLIER: CMC

IDENTIFICATION: 102.4-1974

200

f/f(O) (%1

100

O'--~~~~-'-~~~~--'-~~~~---'-----~~~~-'-~~~~~~~~~-'

0 0.5

SYMBOL PROPERTY

• force to take off

44

I.OX 106

DoselGyl

INITIAL VALVES

8.6 N/25 mm

1.5

Page 47: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

A ADHESIVE TAPE

BASE MATERIAL: Polyethylene terephthalate (PETP), rubber adhesive

TYPE: 1050; Mylar

SUPPLIER: CMC

IDENTIFICATION: 102.4-1974

DESCRIPTION OF MATERIAL: Self-adhesive film for insulation purposes. Film material: polyethylene terephthalate (Mylar). Adhesive: synthetic rubber, thermosetting.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy Is Doses: 5 X 105

, 1 X 106, 5 X 106

, 1 X 107 Gy

METHODS OF TESTING: Pieces of film (115 X 25 mm), stuck to an aluminium support of the same dimensions without heat treat­ment, were irradiated, after which the film was peeled off at a constant rate of 50 mm/min. The bending radius was fixed by a roller of 10 mm diameter and the mean force measured by a tensile testing machine.

RESULTS: Before irradiation, the peeling-off force was 8.6 N for a width of 25 mm. After irradiation, the force reached 150% at 5 X 105 and 1 X 106 Gy. At the higher doses, the base mate­rial (Mylar) Wl\S too brittle to carry out this test, but the film still stuck to the support. There was no change in the colour.

Remarks: For irradiation to higher doses, see also Insulating tape

REFERENCES: 18

APPRECIATION: See Appendix 7

I 11111~11111111 103 104

Dose (Gy)-+

45

Page 48: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

A ADHESIVE TAPE BASE MATERIAL: Polyhydantoin. resin adhesive

TYPE: 6210: Resistofol

SUPPLIER: CMC

IDENTIFICATION: 102.1-1974

f/f(O) 1%1

100

50

OL-~~J__~~~J_~~---'--~~---'--~~~---'--~~-----'-~~-----"-~~-~-----"-~~~

104

SYMBOL

46

105

PROPERTY

force to take off

Dose[Gyl

INITIAL VALUES

8.3 N/25 mm

Page 49: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

A ADHESIVE TAPE

BASE MATERIAL: Polyhydantoin, resin adhesive

TYPE: 621 O; Resistofol

SUPPLIER: CMC

IDENTIFICATION: 102.1-1974

DESCRIPTION OF MATERIAL: Self-adhesive film for insulation purposes. Film material: polyhydantoin (Resistofol). Adhesive: resin type, thermosetting.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position EI in air, dose rate 30 Gy/s Doses: 5 X 105, I X 106

, 5 X 106, 1 X 107 Gy

METHODS OF TESTING: Pieces of film (115 X 25 mm), stuck to an aluminium support of the same dimensions without heat treat­ment, were irradiated, after which the film was peeled off at a constant rate of 50 mm/min. The bending radius was fixed by a roller of 10 mm diameter and the mean force measured by a tensile testing machine.

RESULTS: Before irradiation, the peeling-off force was 8.3 N for a width of25 mm. After irradiation, the film remained flexible until 1 X 107 Gy, but the peeling-off force decreased, reaching less than I% of the initial value at this dose. The colour darkened with the dose.

Remarks:

REFERENCES: 18

APPRECIATION: See Appendix 7

101

Dose (Gy)--+

47

Page 50: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

A ADHESIVE TAPE BASE MATERIAL: Polyimide. resin adhesive

TYPE: 70 IO; Kapton

SUPPLIER: CMC

IDENTIFICATION: 102.2-1974

100

f/f(O) (%1

50

. "' OL--~~-'-----~~~-'-----~~-'--~~-'-~~~-'-~~-'-~~-"-~~~-"-~~-'

48

104

SYMBOL

• PROPERTY

force to take off

Dose[Gyl

INITIAL VALUES

5.6 N/25 mm

107

Page 51: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

A ADHESIVE TAPE

BASE MATERIAL: Polyimide, resin adhesive

TYPE: 7010; Kapton

SUPPLIER: CMC

IDENTIFICATION: 102.2-1974

DESCRIPTION OF MATERIAL: Self-adhesive film for insulation purposes. Film material: polyimide (Kapton). Adhesive: resin type, thermosetting.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy/s Doses: 5 X 10\ 1 X 106

, 5 X 106, 1 X 107 Gy

METHODS OF TESTING: Pieces of film (115 X 25 mm), stuck to an aluminium support of the same dimensions without heat treat­ment, were irradiated, after which the film was peeled off at a constant rate of 50 mm/min. The bending radius was fixed by a roller of 10 mm diameter and the mean force measured by a tensile testing machine.

RESULTS: Before irradiation, the peeling-off force was 5.6 N for a width of 25 mm. After irradiation, the film remained flexible and even retained 45% of its initial adhesive strength at 1 X 107 Gy. However, after this dose, it could not be restuck to the metal. Slight darkening of the colour.

Remarks: At 5 X 107 and 1 X 108 Gy thin films remained flexible, but broke under relatively small tensile force.

REFERENCES: 18

APPRECIATION: See Appendix 7

11~111111 no test 103

Dose (Gy)-+

49

Page 52: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

A ADHESIVE TAPE BASE MATERIAL: Polyimide. resin adhesive

TYPE: Kapton T

SUPPLIER: CMC

IDENTIFICATION: 102.3-1974

200

f/f(O) [%]

100

O·~~~-'--~~~-'--~~~~~~~~~~~~--'----~~~~~-~~~~-·

104

SYMBOL PROPERTY

• force to take off

so

106

Dose!Gyl

INITIAL VALUES

4.3 N/25 mm

107

Page 53: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

A ADHESIVE TAPE

BASE MATERIAL: Polyimide, resin adhesive

TYPE: Kapton T

SUPPLIER: CMC

IDENTIFICATION: 102.3-1974

DESCRIPTION OF MATERIAL: Self-adhesive film for insulation purposes. Film material: polyimide (Kapton T). Adhesive: resin type.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 5 X 105

, l X 106, 5 X 106

, 1 X 107 Gy

METHODS OF TESTING: Pieces of film ( 115 X 25 mm), stuck to an aluminium support of the same dimensions, were irradiated, after which the film was peeled off at a constant rate of 50 mm/min. The bending radius was fixed by a rol­ler of 10 mm diameter and the mean force measured by a tensile testing machine.

RESULTS: Before irradiation, the peeling-off force was 4.3 N for a width of 25 mm. After irradiation, the force increased to about 170% at 106 Gy, but then fell off very rapidly to less than 20% at 107 Gy. Slight darkening of the colour.

Remarks:

REFERENCES: 18

APPRECIATION: See Appendix 7

,-111111111

102 105 107

Dose (Gy)-+

51

Page 54: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Entries and cross-references

Buna, trade name ofChemische Werke HUis AG Synthetic rubber, see Vacuum gasket

Materials listed in General Tables in Appendix 5

Benzene see G-value, p. 23

Bromoform see G-value, p. 23

Butyl rubber see Cable insulation, p. 21 see Elastomer, p. 22 see Hose, p. 25

B

53

Page 55: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Entries and cross-references

CABLE INSULATION Table of general relative radiation effects in Appendix 5 Chloroprene rubber (Neoprene) Ethylene-propylene rubber (EPR) Polyethylene (PE) Polyethylene, cross-linked (XLPE) Polyvinylchloride (PVC) Silicone rubber

CABLE TIE Ethylene-tetrafluoroethylene (ETFE) copolymer Poly amide Polybutylene terephthalate (PBTP) Polyethylene (PE)

CERAMIC Aluminium oxide Asbestos cement Quartz

Cerium doped glass see Glass

CONNECTOR Polyphenylene oxide (PPO) Polyphenylene sulfide (PPS)

COPPER WIRE ETP-Copper (ETP-Cu) OFHC-Copper (OFHC-Cu)

c

55

Page 56: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Materials listed in General Tables in Appendix 5

Carbon tetrachloride see G-value, p. 23

Cellulose esters see Paint, p. 27

Cellulose fibre see Textile, p. 28

Cellulose acetate see Thermoplastic resin, p. 29

Chlorinated rubber see Paint, p. 27

Chlorobenzene see G-value, p. 23

Chlorofluorocarbon oil see Oil, p. 26

Chloroform see G-value, p. 23

Chloroprene rubber (Neoprene) see Cable insulation, p. 21 see Elastomer, p. 22 see G-value, p. 24 see Hose, p. 25 see Paint, p. 27

Chlorosulfonated polyethylene (CSP) see Cable insulation, p. 21 see Elastomer, p. 22 see Paint, p. 27

Cotton see Textile, p. 28

c

Page 57: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE INSULATION

BASE MA TE RIAL: Chloroprene rubber (Neoprene)

TYPE: Cl

SUPPLIER: CERCEM

IDENTIFICATION: 171.2-1974

DESCRIPTION OF MATERIAL: Cable for power supply of l kW electric motor, insulated with chloroprene rubber (Neoprene)

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy/s Doses: 1 X 106 Gy

METHODS OF TESTING: Coiling test, winding ten turns on a core four times the diameter of the cable (Swiss Std. VSM 23 708); searching for defects with a magnifying glass. Bending test, counting the number of 360° backward and forward bends, until damage occurs (Swiss Std. VSM 23780).

RESULTS: Neither the coiling test nor the bending test ( 10 bends) revealed any defect after 106 Gy. No change in colour.

Remarks: See also Part I (Ref. l) for results of tests on similar materials

REFERENCES: 19

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

no ~est 106 107

Dose (Gy)-+

~1

59

Page 58: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE INSULATION BASE MATERIAL: Ethylene-propylene rubber (EPR)

TYPE: 940

SUPPLIER: SILEC

IDENTIFICATION: C 343-1977

10

( MPa) @ 6

(%) ® 4

®

e

1

60

0 5

ABSORBED DOSE (Gy)

5 .,1

MATERIAL: EPR

TYPE: INSULATOR 940

SUPPLIER: SILEC

Remarks:

CURVE PR 0 PERT Y

R Tensile strength

E Elong. at break

H Hardness

Oxygen index

INITIAL VALUE

9.3 MPa

634 %

17

19.5

Shore D

Page 59: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE INSULATION

BASE MATERIAL: Ethylene-propylene rubber (EPR)

TYPE: 940

SUPPLIER: SILEC

IDENTIFICATION: C 343-1977

DESCRIPTION OF MATERIAL: Moulded plates, 2 mm thick. Material used for 1 kV d.c. power cables

APPLICATION AT CERN: Power cable available in CERN stores, SCEM No. 04.08.61.994.1

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 5 X 105

, 1 X 106, 5 X 106 Gy

METHODS OF TESTING: Standard tensile tests on samples of shape-type 2 (ISO/R 527-1966)

RESULTS: At 1 X 106 Gy the elongation at break was reduced by a factor of 2 but was still well above the value of 100%, which has been adopted as the end-point criterion of the useful working range at CERN. The end-point criterion ofIEC 544 (50% of initial value) was reached at 8 X 105 Gy.

Remarks: Example taken from a number of equivalent materials contained in Part I (Ref. 1)

REFERENCES:

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

11111111111111

101 108

Dose (Gy)-+

61

Page 60: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE INSULATION BASE MATERIAL: Polyethylene (PE)

TYPE: Lupolen 1812 DXSK

SUPPLIER: Felten & Guillaume

IDENTIFICATION: C206-1973

62

I

1 ' 0 "J

MATERIAL: PE

TYPE: LUPOLEN 1812 DXSK

SUPPLIER: FELTEN & GUILLAUME

Remarks:

Page 61: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE INSULATION

BASE MATERIAL: Polyethylene (PE)

TYPE: Lupolen 1812 DXSK

SUPPLIER: Felten &Guillaume

IDENTIFICATION: C206-1973

DESCRIPTION OF MATERIAL: Moulded plates, 2 mm thick. Material used as insulation for power cables

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 5 X 105, 1 X 106

, 5 X 106 Gy

METHODS OF TESTING: Standard tensile tests on samples of shape-type 2 (ISO/R 527-1966).

RESULTS: At l X 106 Gy the elongation at break was reduced by a factor of 6 and has reached the value of 100%, which has been adopted as the end-point criterion of the useful working range at CERN. The end-point criterion ofIEC 544 (50% of initial value) was reached at 4 X 105 Gy.

Remarks: Example taken from a number of equivalent materials contained in Part I (Ref. l)

REFERENCES:

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

1!111!1111

Dose (Gy)-+

63

Page 62: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE INSULATION BASE MATERIAL: Polyethylene, cross-linked (XLPE)

TYPE: Unknown

SUPPLIER: BICC

IDENTIFICATION: C 320-1976

( MPa)

(,,)

64

:::~ ~~~::i 'U::!::::: ~ ~>:::~;:~Ti:::::::.::!::: ·::: :::: ::: -:- :::: ·:: ":": ., :::: :::.: :::: ::: :: .. '.::

1,:':: ::. :.:.: :::.: · .. :.:.:_· . .-.. :. ; ::!\_:: ::;::::. :· .. ::: :::· .. : : - - .. w ......... , ... ,

• ·• .... •• .. ,,'"'•I•

~Ht f11Plli~ TI! Hf ;'l;: ::~ t l ; ~ i : '. ~i~ ;~~tc ~~:~ ·--~~ -2+-~,.~:~:~;~;;;T.;~~.!~:;~,;~,;:~;~:.~;~.H.f+-:--'-t--!'-'+-+--+-+'-IH-H-1

l-"--.F.c;.;:::+-::.i;it-.. flii.:·lt'·-"-:··+·;;; .. 14++++- ···· -~- ·· - ··· .............

ABSORBED DOSE (Gy)

MATERIAL: XLPE

TYPE: INSULATOR

SUPPLIER: BICC

Remarks:

CURVE PR 0 P E R T Y

R

E

H

Tensile strength

Elong. at break

Hardness

Oxygen index

INITIAL VALUE

20.8

450

39

19.0

MPa

Shore D

Page 63: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE INSULATION

BASE MATERIAL: Polyethylene, cross-linked (XLPE)

TYPE: Unknown

SUPPLIER: BICC

IDENTIFICATION: C 320-1976

DESCRIPTION OF MATERIAL: Moulded plates, 1.5 mm thick. The material was proposed for the insulation oflow-voltage power cables

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 5 X 105

, 1 X 106, 5 X 106 Gy

METHODS OF TESTING: Standard tensile tests on samples of shape-type 2 (ISO/R 527-1966)

RESULTS: At 8 X 105 Gy the elongation at break was reduced by a factor of 2, and at 2 X 106 Gy it reached the value of 100%, which has been adopted as the end-point criterion of the useful working range at CERN. The end-point criterion of IEC 544 (50% of initial value) was reached at 8 X 105 Gy.

Remarks: Example taken from a number of equivalent materials contained in Part I (Ref. 1)

REFERENCES:

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

11111111111!

101 106 108

Dose (Gy)-+

65

Page 64: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE INSULATION

BASE MATERIAL: Polyethylene, cross-linked (XLPE)

TYPE: C2

SUPPLIER: CERCEM

IDENTIFICATION: 171.3-1974

DESCRIPTION OF MATERIAL: Cable for power supply of 1 kW electric motor, insulated with chemically cross-linked polyethylene (XLPE)

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 1 X 106 Gy

METHODS OF TESTING: Coiling test, winding ten turns on a core four times the diameter of the cable, and searching for defects with a magnifying glass (Swiss Std. VSM 23 708). Bending test, counting the number of 360° backward and forward bends until damage occurs (Swiss Std. VSM 23780).

RESULTS: Neither the coiling test nor the bending test (10 bends) revealed any defect after 106 Gy. No change in colour.

Remarks: See also previous entry and Part I (Ref. 1) for results of tests on similar materials

REFERENCES: 19

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

no ~est 105 107

Dose (Gy)-+

~1

67

Page 65: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE INSULATION BASE MATERIAL: Polyvinyl chloride (PVC)

TYPE: S34

SUPPLIER: Felten & Guillaume

IDENTIFICATION: C 204-1974

(MPa) @

(%) ®

®

t204

' I I

~:n~~':i 6 +-~--+-+---t-+-t-i'-t-1-+-- 1 " .--'-----L-__J____J_J - - ~f +--__.__.___'-'--+-i-1-1-+--~-+--r-1--l~ i I

Tl 0

68

... __ J ____ -··

I 5

l : '

ABSORBED DOSE (Gy)

5

·j'; 11 . I,

1 I l I I . j I

107

MATERIAL: PVC

TYPE: Wrnuur FILLER, S34

SUPPLIER: FELTEN & GUILLAUME

Remarks:

CURVE PROPERTY INITIAL VALUE

R Tensile strength 14.8 ;.:?a

E Elong. at break 256 ,, H Hardness 45 Shore

Oxygen index

D

Page 66: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE INSULATION

BASE MATERIAL: Polyvinyl chloride (PVC)

TYPE: S34

SUPPLIER: Felten & Guillaume

IDENTIFICATION: C 204-1974

DESCRIPTION OF MATERIAL: Moulded plates, 2 mm thick

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 5 X 105

, IX 106, 5 X 106 Gy

METHODS OF TESTING: Standard tensile tests on samples of shape-type 2 (ISO/R 527-1966)

RESULTS: At I X 106 Gy the elongation at break was reduced by a factor of 2 but was still well above the value of 100%, which has been adopted as the end-point criterion of the useful working range at CERN. The end-point criterion oflEC 544 (50% of the initial value) W?-'> reached at 8 X 105 Gy. Because of the considerable amount of corrosive hydrochloric acid (HCl) vapours released at high irradiation levels as well as during a possible fire, the use of this material is no longer recommended.

Remarks: Example taken from a number of equivalent materials contained in Part I (Ref. 1)

REFERENCES:

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

1111111\lllillll

105 106

Dose (Gy)-+

69

Page 67: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE INSULATION BASE MATERIAL: Silicone rubber

TYPE: SR 1

SUPPLIER: Draka

IDENTIFICATION: C 134-1973

( MPa)

(t.)

10

"" ................. ..

• H+i YH ~, ,, :f ~,: , ... · · . · · : : : : :::~ H:: 11 i~:~ ~~~ :,

._IEO DOSE (Gr)

MATERIAL: SILICONE RUBBER

TYPE: SRI

SUPPLIER: DRAKA

Remarks:

CURVE f'ROPEATY INITIAL

R B.5

E E•ae.•.._. 637

H ........... o., .. n inde«

VALUE

Mfl• .. ShoreC,D

Page 68: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE INSULATION

BASE MATERIAL: Silicone rubber

TYPE: SR 1

SUPPLIER: Draka

IDENTIFICATION: C 134-1973

DESCRIPTION OF MATERIAL: Moulded plates, 2 mm thick

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy Is Doses: 5 X 105

, 1 X 106, 5 X 106 Gy

METHODS OF TESTING: Standard tensile tests on samples of shape-type 2 (ISO/R 5 2 7-1966)

RESULTS: At 5 X 105 Gy the elongation at break was reduced to 100°!0, which has been adopted as the end-point criterion of the useful woning range at CERN. The end-point criterion oflEC 544 (50% of the initial value) was reached at 2 X 105 Gy. At 5 X 106 Gy, no tests were possible owing to brittleness.

Remarks: Example taken from a number of equivalent materials contained in Part I (Ref. 1)

REFERENCES:

APPRECIATION: •••USE IN HIGH LEVEL RAD/A TION AREAS NOT RECOMMENDED••• See Appendix 7

Degradation of mechanical properties:

Dose (Gy)-+

71

Page 69: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE INSULATION

BASE MATERIAL: Silicone rubber

TYPE: C3

SUPPLIER: CERCEM

IDENTIFICATION: 171.4-1974

DESCRIPTION OF MATERIAL: Cable for power supply of I kW electric motor, insulated with silicone rubber

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 1 X 106 Gy

METHODS OF TESTING: Coiling test, winding ten turns on a core four times the diameter of the cable, and searching for defects with a magnifying glass (Swiss Std. VSM 23 708). Bending test, counting the number of 360° backward and forward bends until damage occurs (Swiss Std. VSM 23780).

RESULTS: Before irradiation, neither tests revealed any damage. After a dose of 1 X 106 Gy, the insulation broke everywhere when bending was attempted for both tests. No change in colour.

Remarks: See also previous entry and Part I (Ref. 1) for results using similar materials

REFERENCES: 19

APPRECIATION: ***USE IN HIGH LEVEL RADIATION AREAS NOT RECOMMENDED"'** See Appendix 7

Degradation of mechanical properties:

111111111

10'

Dose (Gy)-+

73

Page 70: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE INSULATION

BASE MA TERI AL: Silicone rubber

TYPE: C4

SUPPLIER: CERCEM

IDENTIFICATION: 171.5-1974

DESCRIPTION OF MATERIAL: Cable for power supply of I kW electric motor, insulated with silicone rubber

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy Is Doses: l X 106 Gy

METHODS OF TESTING: Coiling test, winding ten turns on a core four times the diameter of the cable, and searching for defects with a magnifying glass (Swiss Std. VSM 23 708). Bending test, counting the number of 360° backward and forward bends until damage occurs (Swiss Std. VSM 23780).

RESULTS: Before irradiation, no defects were detected with either test ( l 0 bends for the bending test). After 1 X 106 Gy, the coiling test revealed one crack only, whereas in the bending test, one bend was suf­ficient to break the cable. No change in colour.

Remarks: See also previous entry and Part I (Ref. 1) for results of tests on similar materials

REFERENCES: 19

APPRECIATION: ***USE IN HIGH LEVEL RAD/A TION AREAS NOT RECOMMENDED*** See Appendix 7

Degradation of mechanical properties:

111111111

101 102 104 10~ 106 10 7 108

Dose (Gy)--.

75

Page 71: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE TIE

BASE MATERIAL: Ethylene-tetrafluoroethylene (ETFE) copolymer

TYPE: KR 6118; Tefzel

SUPPLIER: Hellermann

IDENTIFICATION: 109.3-1974

DESCRIPTION OF MATERIAL: Cable ties made from ethylene-tetrafluoroethylene copolymer (Tefzel) to be used for 40 mm diameter cable bundles

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy/s Doses: 1 X 106

, 5 X 106 Gy

METHODS OF TESTING: Bending tests around a 20 mm diameter core, counting the number of bends until breaking occurs. Straight samples and samples closed to 40 mm diameter were irradiated.

RESULTS: No tests were made before irradiation. After 1 X 106 Gy, 10 bends were made before breaking occurred. At 5 X 106 Gy, the material became very brittle and broke when bending was attempted; the closed samples broke when a slight pressure was applied. The colour changed from transparent to light yellow.

Remarks:

REFERENCES: 20

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

11111111111111111

101 106 108

Dose (Gy)-+

77

Page 72: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE TIE BASE MATERIAL: Ethykne-tetranuoroetllykne ( ETFE) -:orolyrner

TYPE: TY-RAP: Tefzel

SUPPLIER: T & B

IDENTIFICATION: 106.2-1978

f/f(O) 1%1

78

100

50

0 104

SYMBOL

• •

-r------~--~----

• •

-------

10~ IO" DosciGyl

PROPERTY INITIAL VALUES

number of bends > 100 hardness 66 Shore D

107

Page 73: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Ethylene-tetrafluoroethylene (ETFE) copolymer

TYPE: TY-RAP; Tefzel

SUPPLIER: T & B

IDENTIFICATION: 106.2-1978

DESCRIPTION OF MATERIAL: Cable ties made from ethylene-tetrafluoroethylene copolymer (Tef zel)

APPLICATION AT CERN: Securing of cables in the Super Proton Synchrotron LSS2, LSS6 and neutrino cave

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy/s Doses: 5 X 105

, 1 X 106, 5 X 106

, 1 X 107 Gy

METHODS OF TESTING: Bending test, counting the number of 180° bends until breaking occurs. Shore hardness test.

RESULTS: Before irradiation, there was still no break in the cable tie after 100 bends. At 1 X 106 Gy, it broke after 20 bends. At 5 X 106 Gy, the material was unusable. The colour changed from initial light green to dark green at the highest dose.

c CABLE TIE

Remarks: According to the manufacturer, the tensile strength is increased by irradiation up to 106 Gy.

REFERENCES:

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

111111111111111111111

101 103 106 107

Dose (Gy)-+

79

Page 74: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE TIE BASE MATERIAL: Poly amide

TYPE: -

SUPPLIER: -

IDENTIFICATION: 107-1975

f/f(O) [%]

100

50

O·~~--'-~~~---~~---~~----'-~~~-'------~~-'------~------'~~-----~~-·

80

104

SYMBOL

• PROPERTY

number of bends

Dose[Gy]

INITIAL VALUES

100

107

Page 75: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE TIE

BASE MATERIAL: Poly amide

TYPE: -

SUPPLIER: -

IDENTIFICATION: 107-1975

DESCRIPTION OF MATERIAL: Cable ties made from white polyamide (Nylon), two rolled to 45 mm diameter, three normal straight

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 5 X 105

, l X 106, 5 X 106 Gy

METHODS OF TESTING: Bending tests, counting the number of 360° bends around a 2-3 mm diameter core until breaking occurs

RESULTS: Before irradiation, 100 bends were needed to break the cable tie. At l X 106 Gy, 40 bends were made before breaking occurred; and at 5 X 106 Gy, it broke after 10 bends. Colour changed to yellow (after first two doses) and then to brown.

Remarks:

REFERENCES: 20

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

11111111111111111111

103 107

Dose ( Gy) --+

81

Page 76: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE TIE

BASE MATERIAL: Polybutylene terephthalate (PBTP)

TYPE: KR 4000

SUPPLIER: Hellermann

IDENTIFICATION: 108.2-1974

DESCRIPTION OF MATERIAL: Cable ties made from polybutylene terephthalate (PBTP); 68 kg

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate approx. 10 Gy/s Doses: I X 106 Gy

METHODS OF TESTING: Bending tests around a 20 mm diameter core, counting the number of bends until breaking occurs. Straight samples and samples closed to 40 mm diameter were irradiated.

RESULTS: Before irradiation, there was still no break in the cable tie after I 00 bends. At I X 106 Gy, it broke at 10 bends. Closed samples in good condition.

Remarks:

REFERENCES: 20

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

lllllllllllllllll -101 103 106

Dose (Gy)-+

108

83

Page 77: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE TIE

BASE MATERIAL: Polyethylene (PE)

TYPE: KR 6/ IO; Hostalen

SUPPLIER: Hellermann

IDENTIFICATION: IOS.1-1974

DESCRIPTION OF MATERIAL: Cable ties made from low-pressure polyethylene (Hostalen); 35 kg

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched off reactor position 35 in air, dose rate approx. IO Gy/s Doses: 1 X I06 Gy

METHODS OF TESTING: Bending test around a 20 mm diameter core, counting the number of bends until breaking occurs. Straight samples and samples closed to 40 mm diameter were irradiated.

RESULTS: Before irradiation, there was still no break in the cable tie after IOO bends. At 1 X I06 Gy, about 50 bends were necessary before breaking occurred. Closed samples in good condi­tion. The colour remained unchanged.

Remarks:

REFERENCES: 20

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

IO' 106 108

Dose (Gy)--+

85

Page 78: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE TIE

BASE MATERIAL: Polyethylene (PE)

TYPE: -

SUPPLIER:

IDENTIFICATION: 109.1-1974

DESCRIPTION OF MATERIAL: Cable ties made from polyethylene, to be used for 40 mm diameter cable bundles

APPLICATION AT CERN: Securing of wiring in termination racks

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy Is Doses: 1 X 106

, 5 X 106 Gy

METHODS OF TESTING: Bending tests around a 20 mm diameter core, counting the number of bends until breaking occurs. Straight samples and samples closed to 40 mm diameter were irradiated.

RESULTS: Before irradiation, there was still no break in the cable tie after 100 bends. At 1 X 106 Gy, about 5 bends were made before breaking occurred; and after 5 X 106

, it broke after two bends. Closed samples in good condition. The colour changed from white to light yellow and dark yellow.

Remarks:

REFERENCES: 20

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

1111111!111!111:1

101 10~ 106

Dose (Gy)-+

87

Page 79: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CABLE TIE

BASE MATERIAL: Polyethylene (PE)

TYPE: P 5206 S; Vestolene

SUPPLIER: Hellermann

IDENTIFICATION: 109.2-1974

DESCRIPTION OF MATERIAL: Cable ties made from polyethylene (Vestolene), to be used for 40 mm diameter cable bundles. Special fire-resistant type.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: I X 106

, 5 X 106Gy

METHODS OF TESTING: Bending tests around a 20 mm diameter core, counting the number of bends until breaking occurs. Straight samples and samples closed to 40 mm diameter were irradiated.

RESULTS: Before irradiation, there was still no break in the cable tie after 100 bends. Already at I X 106 Gy, breaking occurred before the first bend. The colour changed from light grey to brown. The curved samples were broken without application of special forces, either due to elastic stress alone or during handling.

Remarks: High induced remanent radioactivity.

REFERENCES: 20

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

111111111111111111!111

106

Dose (Gy)-+

89

Page 80: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Polyethylene (PE)

TYPE: D

SUPPLIER: Hellermann

IDENTIFICATION: 106.1-1978

DESCRIPTION OF MATERIAL: Cable ties made from a polyethylene derivative

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 5 X 105, 1 X 106

, 5 X 106, 1 X 107 Gy

METHODS OF TESTING: Bending test, counting the number of 180° bends until breaking occurs. Shore hardness test.

RESULTS: Before irradiation, there was still no break in the cable tie after 100 bends.

c CABLE TIE

Already after 5 X 105 Gy it broke at the first bend, becoming more and more brittle at the higher doses. Colour changed from transparent before irradiation, over light yellow at 5 X 105 Gy, to brown at 1X107 Gy. Shore hardness increased from 59 D at zero dose to 64 D at 5 X 105 Gy, and to 70 D and more at 1 X 10 6Gy and above.

Remarks:

REFERENCES:

APPRECIATION: ***USE IN HIGH-LEVEL RAD/A TION AREAS NOT RECOMMENDED*** See Appendix 7

Degradation of mechanical properties:

notes

10' 103 106 108

Dose (Gy)-+

91

Page 81: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CERAMIC

BASE MATERIAL: Aluminium oxide

TYPE: -

SUPPLIER: -

IDENTIFICATION: 112-1974

DESCRIPTION OF MATERIAL: Tubes of dimensions 75 X 2 X 17 0 and 50 X 2 X 12 0 (in mm) made from 99.5% pure Al20 3were used as substrate for resistive coating

APPLICATION AT CERN: With NiCr coating, used as dumping resistors in the SPS vacuum system m large quantities (> 2000 pieces)

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position 11 in water, dose rate 400 Gy/s Doses: 1 X 108 Gy

METHODS OF TESTING: Visual inspection

RESULTS: No defects found

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

Dose (Gy)-+

108

93

Page 82: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Aluminium oxide

TYPE: Unknown

SUPPLIER: Unknown

IDENTIFICATION: 111.6-1973

DESCRIPTION OF MATERIAL: Aluminium oxide 99.5% (Al20 3), of dimension 8 0 X 90 (in mm)

APPLICATION AT CERN: General applications (available from CERN stores, SCEM No. 19.63.26.081)

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position 11 in water, dose rate 300 Gy/s Doses: 5 X 107

, 1 X 108 Gy

METHODS OF TESTING: Three-point flexural test, similar to ISO 1 78

RESULTS: Flexural strength: 250 N/mm2

Modulus of elasticity: 1 X 105 N/mm2•

No changes after irradiation up to 1 X 108 Gy.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

102

Dose (Gy)-+

c CERAMIC

10'

95

Page 83: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Asbestos cement

TYPE: -

SUPPLIER: -

IDENTIFICATION: 111.11-1973

DESCRIPTION OF MATERIAL: Asbestos and cement composite material

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position 11 in water, dose rate 300 Gy/s Doses: 5 X 107

, 1 X 108 Gy

METHODS OF TESTING: Three-point flexural test, similar to ISO 1 78

RESULTS: Flexural strength: 44 N/mm 2

Modulus of elasticity: 8 X 103 N/mm2•

c CERAMIC

At 1 X 108Gy: Flexural strength decreases by 25% and modulus of P.lasticity increases by 70%.

Remarks: Results probably influenced by irradiation in water

REFERENCES:

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

106

Dose (Gy)-+

97

Page 84: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Quartz

TYPE: -

SUPPLIER: -

IDENTIFICATION: 111.7-1973

DESCRIPTION OF MATERIAL: Vacuum fused high-purity quartz, of dimensions 5 0 X 80 (in mm)

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position 11 in water, dose rate 300 Gy/s Doses: 5 X 107

, 1 X 108 Gy

METHODS OF TESTING: Three-point flexural test, similar to ISO 1 78

RESULTS: Flexural strength: 70 N/mm2

Modulus of elasticity: 4. 7 X 104 N/mm2•

No major changes due to irradiation up to 1 X 108 Gy.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

101 104

Dose (Gy)-+

c CERAMIC

99

Page 85: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CONNECTOR

BASE MATERIAL: Polyphenylene oxide (PPO)

TYPE: -; Nary!

SUPPLIER: -

IDENTIFICATION: 20.1-1975

DESCRIPTION OF MATERIAL: Inserts for BNC connectors, made from Nary! (polyphenylene oxide, PPO)

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate 10 Gy/s Doses: 1 X 106

, 5 X 106 Gy

METHODS OF TESTING: Connection test

RESULTS: No damage observed

Remarks: According to data published in Ref. 37, this material is radiation-resistant up to 5 X 107 Gy

REFERENCES:

APPRECIATION: See Appendix 7

111111111

101 102 106 107 108

Dose (Gy)-+

101

Page 86: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c CONNECTOR

BASE MATERIAL: Polyphenylene sulfide (PPS)

TYPE: -; Ryton

SUPPLIER: -

IDENTIFICATION: 123-1975

DESCRIPTION OF MATERIAL: Inserts for multipin connectors, made from Ryton (polyphenylene sulfide, PPS) with 40% glass-fibres (Ryton-R-4)

APPLICATION AT CERN: General application (available in CERN Stores, SCEM No. 09.31.05)

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position 11 in water, dose rate400 Gy/s Doses: 1 X 106

, 1 X 107, 5 X 107 Gy

METHODS OF TESTING: Multiple connection test (up to 5 X 107 Gy). Insulation resistance (after 106 Gy). Breakdown voltage (after 106 Gy).

RESULTS: No damage was observed up to 5 X 107 Gy. At 1 X 106 Gy, mechanical and electrical tests were performed by the supplier. No damage was observed. Insulation resistance > 5 X 109 n, dielectric breakdown voltage > 2000 V a.c.

Remarks: See also Part II (Ref. 2) for further test results on Ryton

REFERENCES:

APPRECIATION: See Appendix 7

;-J no test <----'--~-'---'-~L---L~.L----~~-L~L---L~-'---'-~~-'--~~---'-~-'----~~-

103 104 107 10 s

Dose (Gy)-+

103

Page 87: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c COPPER WIRE BASE MATERIAL: Copper

TYPE: OFHC and ETP

SUPPLIER:

IDENTIFICATION: 239-1975

6 OFHC [cold drawn}

~5 0

0 1.0

6 weeks after irradiation 6

.._

0 10 20

6 weeks after irradiation

2.0 3.0 4.0x1023 m-Neutron fluence [ E > 0.1 HeVJ

OFHC [cold drawnr

30 40 50x1023 m-2

Neutron fluence [ E > 01 He VJ

SYMBOL PROPERTY INITIAL VALUES REMARKS

I04

resistivity (I = 100 mA) at 22 °C

not measured

ETP annealed OFHC cold drawn

ETP cold drawn OFHC annealed

Page 88: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

c COPPER WIRE

BASE MATERIAL: Copper

TYPE: OFHC and ETP

SUPPLIER:

IDENTIFICATION: 239-1975

DESCRIPTION OF MATERIAL: Wires of0.4 mm diameter, cold-drawn from oxygen-free high-conductivity (OFHC) copper (99.96%) and from electrolytic tough-pitch (ETP) copper (99.92%), with and without a following anneal at 300 °C

APPLICATION AT CERN: Similar material used for the Super Proton Synchrotron septum magnets

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, high-flux core position; flux: 7 X 1017 n/m2 s (E > 0.1 MeV) Fluences: between 0. 7 and 5.5 X 1023 n/m2

METHODS OF TESTING: Resistance bridge measurements at a current I < 100 mA on wire samples oflengths varying from 1.5 to 5 m. During irradiation the wires were loosely coiled inside an aluminium container of 20 mm diameter in close contact with the wall. The container was filled with He gas at 105 Pa, and was cooled with the pool cooling-water at 40 °C.

RESULTS: The increase in resistance was most pronounced in the high-purity annealed material, 4% at 1 X 1023 n/m2 corresponding to about 3 X 106 Gy from fast neutrons. In the ETP-type, the effect was 30% lower; and in the non-annealed samples, only 1.5% for both materials. See figures on opposite page (Ref. 10).

Remarks: A fluence of 1023n/m 2corresponds to 2.6 X 106 Gy in copper or 4 X 108 Gy in organic (CH2) 0

materials

REFERENCES: 10

APPRECIATION: See Appendix 7

101 105

Dose (Gy)-+

108

105

Page 89: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Di ala C, trade name of Shell Mineral oil, see Insulating oil

Diester oil see Lubricating oil

Entries and cross-references

Materials listed in General Tables in Appendix 5

Dacron, trade name of Du Pont Polyethylene terephthalate, see Textile, p. 28

Dichloroethane see G-value, p. 23

Dichlorobenzene see G-value, p. 23

Dynel, trade name of Union Carbide Chemicals Corp. see Textile, p. 28

D

107

Page 90: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Entries and cross-references

Elastomer Table of general relative radiation effects in Appendix 5

ELECTRONICS COMPONENTS

Epoxy resin see Paint see Thermosetting resin see Vacuum chamber tube see Vacuum pump accessory

Ethylene-propylene rubber (EPR) and (EPDM) see Cable insulation see Hoses see Seal see Valve

Ethylene-tetrafluoroethylene copolymer (ETFE) see Cable tie

E

109

Page 91: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Materials listed in General Tables in Appendix 5

Epoxy resin see Paint, p. 27 see Thermosetting resin, p. 30

Esters see Oil, p. 26

Ethers see Oil, p. 26

Ethyl bromide see G-value, p. 23

Ethylene-chlorotrifluoroethylene (E-CTFE) see Cable insulation, p. 21

Ethylene-propylene polyallomer see Thermoplastic resin, p. 29

Ethylene-propylene rubber (EPR) and (EPDM) see Cable insulation, p. 21 see Elastomer, p. 22 see Hose, p. 25

Ethylene-tetrafluoroethylene (ETFE) see Cable insulation, p. 21

Ethylene vinyl acetate (EV A) see Cable insulation, p. 21

E

111

Page 92: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

E ELECTRONICS COMPONENTS BASE MATERIAL: Selenium

TYPE: HV diode

SUPPLIER: -

IDENTIFICATION: 18-19 78

150~--------~----

f/f(O) [%1

50

0 0 1.0 2.0X 104

Dose!Gyl

SYMBOL PROPERTY INITIAL VALUES

• Vr(0.01 A) 100 v • I,(5 kV) lOOµA

112

3.0

Page 93: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

E ELECTRONICS COMPONENTS

BASE MATERIAL: Selenium

TYPE: HV diode

SUPPLIER:

IDENTIFICATION: 18-1978

DESCRIPTION OF MATERIAL: High-voltage rectifier stack of selenium diodes

APPLICATION AT CERN: High-voltage d.c. power supplies for use in high-level radiation areas

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, standard neutron irradiation facility (SNIF); flux: 4 X 1013 n/m 2 s (E > l MeV)

Doses: 5 X 1018 n/m 2 (E > 1 MeV)

METHODS OF TESTING: Measurement of forward voltage drop Yr at a current of 10 mA. Measurement ofreverse current Ir at a voltage of 5 kV.

RESULTS: Up to a fluence of 5 X 1018 n/m2 (E > l MeV) there is no deterioration of the tested electrical properties; instead, there is a slight improvement. This fluence corresponds to 130 Gy in selenium or 2.1 X 104 Gy in (CH2)n materials

Remarks: More data on radiation effects on electronics components can be found in Refs. 5, 6, 8, 21, 38 and41

REFERENCES:

APPRECIATION: See Appendix 7

no !est ~1 101

Dose (Gy)-+

113

Page 94: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

E ELECTRONICS COMPONENTS BASE MATERIAL: Silicon

TYPE: -

SUPPLIER: -

IDENTIFICATION: 14-1979

100

f/f(O) [dB]

50

O·~~-'-~-'E-~~~~-'--~~-----'---~--'~~~~~~~--'-~-----'---~~~~-I01

Dose[Gyl

SYMBOL PROPERTY INITIAL VALVES

e forward voltage drop ( 100 mA) 0. 76 V • reverse current ( 1 kV) 50 nA

For both properties, y = 20 log f/f(O) has been plotted (decibels)

114

105

STD. DEV.

< ± 1.5 dB < ±5dB

Page 95: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

E ELECTRONICS COMPONENTS

BASE MATERIAL: Silicon

TYPE: -

SUPPLIER:

IDENTIFICATION: 14-1979

DESCRIPTION OF MATERIAL: Rectifier diode for l kV

APPLICATION AT CERN: Rectifier diodes for use in power supplies that are subject to low-level radiation doses only

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, standard neutron irradiation facility (SNIF); flux: 4 X 1013 n/m 2 s (E > l MeV)

Doses: 1016, 1017

, 10 18, 1019 n/m2 (E > l MeV)

METHODS OF TESTING: Forward voltage drop Vrat 100 mA forward current. Reverse current Ir at reverse voltage of 1 kV.

RESULTS: The reverse current increases almost linear with fluence, whereas the forward voltage drop increases slowly up to 1017 n/m2

, then accelerates considerably, reaching about 70 Vat 1018 n/m 2•

At 1019 n/m2, the rectifier is destroyed. This fluence corresponds to a dose of 1200 Gy from fast neut­

rons in silicon or 4.1 X 104 Gy in (CH2)n material.

Remarks: More data on radiation effects on electronics components can be found in Refs. 5, 6, 8, 21, 38, and41

REFERENCES:

APPRECIATION: ***USE IN RAD/A TION AREAS NOT RECOMMENDED*** See Appendix 7

-•111111111111111111111i:1 101 102 103

Dose (Gy)-+

115

Page 96: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

E ELECTRONICS COMPONENTS BASEMATERIAL: Various

TYPE: See table below

SUPPLIER: Various

IDENTIFICATION: 133-1974

Designation

Resistor: carbon metal film wire wound potmeter "cermet"

Capacitor: ceramic mica polyester polycarbonate MKL electrolytic Al tantalum

Diode: rectifier, Si general-purpose, Si general-purpose, Si hot carrier, Si Zener, Si tunnel, Ge

Transistor: NPN, Si PNP, Si, rad. resist. PNP, Si, rad. resist. FET, Si, N-channel FET, Si, P-channel MOSFET, P-channel MOSFET, N-channel

Integrated: ITL gate ITL flip-flop ITLcounter ITL one-shot ITLgate ITL flip-flop amplifier, rad. res. amplifier, rad. res. op. ampli. rad. res. op. ampli. rad. res. op. ampli. FET input op. ampli. gen. purpose comparator op. ampli. op. ampli. op. ampli. FET input

Discrete: op. ampli. DAC. 10 bits

Rectifier: selenium

Type

I k0,5% lk0,1% HXHl, 5% I kO, 78P 20nF, 30V 22 pF, 300 V 15nF,125V 15 nF, 250 V 0.22µF, IOOV 200µF, IOV 15µF,20V IOD6 IN914 BAY72 HP2900 ZF6,8 IN3717 2N918 2N5332 MM4261H 2N3819 2N3820 3Nl65 BSV81 SN7400N SN7473N SN7493N SN74121N MC3000P MC3055P RSN55900 RSN55910 RSN52709 µA744 µA740 MC174l SN72710 Tl303 Tl3 l9 Tl420 Tl024 T4022 B250C75

Exposure in n/m2 (E > l MeV) *)

1016 10 17 1018 1019

. . ·.· ,· .. ··-: >~-:

t..

I•· . ··.·:••::·:.::~/~$$& [· ... ::::>·.'.:'."·· ·.·'.···::·:>:>)

. ·.·.·t:z;Vff~A'Wh t· ······v////~A

f": . .... ··.·.-.'.'.·.<-::~~~ I %····· .... ~/A

I.·· ··.··~Ml

- -V././././././././././/./././/,

-V.///#././/h. --V.//././././/./h

-V.//./././///././/./././h'.

--'V/./././///././/,

--V.////././h

--'V///.///././h

WW~hW42 ~~,.:%

~A? ~A

t V~?

::;;"./././/././././././/./././/.///h

V././././././././././././//././/h.

0 ) Conversion factor IO" n/m 2 (E > 1 McV)::::: 410 Gy in organic (CH,)n materials or 12 Gy in silicon .

..._... ......... ~~-' ~ stable damaged broken

116

Page 97: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

E ELECTRONICS COMPONENTS

BASE MATERIAL: Various

TYPE: See table on opposite page

SUPPLIER: Various

IDENTIFICATION: 133-1974

DESCRIPTION OF MATERIAL: Resistor, capacitor, diode, transistor, integrated TTL circuit, discrete monolithic units. selenium recti­fier.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, standard neutron irradiation facility (SNIF); flux: 4 X 10 13 n/m 2 s (E >I MeV); dose rate: 0.4 Gy/s

Doses: Various METHODS OF TESTING:

See reference

RESULTS: See table on opposite page

Remarks: More data on radiation effects on electronics components can be found in Refs. 5, 6, 8, 21, 38, and41

REFERENCES: 8

APPRECIATION: ***USE IN RAD/A TION AREAS NOT RECOMMENDED*** See Appendix 7

-111111111111111111111 101 104 106 107

Dose (Gy)-+

117

Page 98: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Fluorinated oil see Insulating oil see Vacuum seal

Fluorinated polymer see Cable tie

FOAM

see Heating element see Seal see Vacuum seal

Polyurethane foam

Entries and cross-references

Materials listed in General Tables in Appendix 5

Flamtrol, trade name of Raychem Polyolefin, see Cable insulation, p. 21

Fluorinated compounds see Cable insulation, p. 21 see Elastomer, p. 22 see Hose, p. 25 see Oil, p. 26 see Thermoplastic resin, p. 29

F

119

Page 99: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Polyurethane foam

TYPE: Non-elastic

SUPPLIER: Unknown

IDENTIFICATION: 40-1978

DESCRIPTION OF MATERIAL: Test samples of PUR foam used for thermal insulation of tubings, non-elastic type

APPLICATION AT CERN: Used for insulation of tubings in Super Proton Synchrotron tunnel neutrino cave

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy/s Doses: 5 X 105

, 1 X 106 Gy

METHODS OF TESTING: Qualitative, mechanical and visual

RESULTS:

F FOAM

Visual appearance was unchanged after irradiation without mechanical forces applied; slight darkening of colour. At 1 X 106 Gy, the foam was very brittle and crumbled easily.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

111111111

105

Dose (Gy)-+

121

Page 100: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Entries and cross-references

G-value Table of general relative radiation effects in Appendix 5

GLASS Cerium-doped glass see also Optical fibre

Glass fibre see Optical fibre

G

123

Page 101: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

G GLASS BASE MATERIAL: Cerium-doped glass

TYPE: See table

SUPPLIER: Chance-Pilkington; Schott & Gen.

IDENTIFICATION: 146-1974

Types of glass (in order of increasing Ce content) and reduction oflight transmission (A. = 450 nm) in percent at l X 106

, 1 X 107, and 5 X 107 Gy. (Manufacturer: Schott, except Nos. 9 and 10: Pilkington.)

No. Glass type Ce0 2 content

Reduction oflight transmission (A. = 450 nm) in percent at a dose of

IX l06 Gy81 1 X 107 Gyb1 5 X 107 Gyb1

9 RSF 0.5 60 63 78

16 SF 19G7 0.7 13 26 30

18 SF8G7 0.7 11 12 12

19 SF IG7 0.7 0 22 21

3 WG9G9 0.9 4 20 29

12 SK IOGIO 1.0 10 23 37

5 BAK I Gl2 1.2 2 12 13

14 F2Gl2 1.2 3 5 6

15 SF 16Gl2 1.2 3 3 12

8 SK4Gl3 1.3 7 28 49

I BK 7Gl4 1.4 2 13 21

7 LF 5 Gl5 1.5 0 6

17 LAK N9Gl5 1.5 18 64 74

10 OW 10 1.7 7.3 22.5 32

II F2G20 2.0 0 3

2 BK 7G25 2.5 0 13 16

4 GG375G34 3.4 I 8 24

6 LF4G34 3.4 3 11 15

13 F6G40 4.0 2 9 11

a) Reactor irradiation position EI b) Reactor irradiation position 11

For both (a) and b) irradiation positions, the exposure dose in organic (CHJ" materials is given, which will represent the true dose from y-radiations in these glasses within measurement error. The transmission values are normalized for a thickness of 2.5 mm.

124

Page 102: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Cerium-doped glass

TYPE: See table opposite page

SUPPLIER: Chance-Pilkington; Schott & Gen.

IDENTIFICATION: 146-1974

DESCRIPTION OF MATERIAL: Glass with cerium content varying from 0.5% to 4.0%

APPLICATION AT CERN: Windows for beam observation equipment

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, 30 Gy/s; position 11 in water, 300 Gy/s Doses: 5 X 104, 1 X 105, 5 X 105

, I X 106, 5 X 106

, 1 X 107, 5 X 107 Gy

METHODS OF TESTING: Percentage change in spectral transmission between 350 nm and 550 nm

RESULTS: No effect up to 106 Gy. Reduction in light transmission of less than 10% at 107 Gy. Reduction oflight transmission ofless than 20% at 5 X 107 Gy. For details, see table on opposite page.

Remarks: More data and transmission spectra can be found in Ref. 9

REFERENCES: 9

APPRECIATION: See Appendix 7

G GLASS

111111111~11111111111111111111 101 108

Dose (Gy)-+

125

Page 103: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

HEATING ELEMENT Teflon

HF ABSORBER

HOSE

Entries and cross-references

Ethylene-propylene rubber (EPR)/glass fibre EPR/Kevlar fibre EPR/polyester fibre Polyethylene terephthalate copolymer

Hostalen, trade name of Hoechst Polyethylene, see Cable tie

Hypermalloy see Magnetic material

Hytrel, trade name of Du Pont Polyethylene terephthalate copolymer see Hose

Materials listed in General Tables in Appendix 5

Halar, trade name of Allied Chemical Ethylene-chlorotrifluoroethylene see Cable insulation, p. 21

Hypalon, trade name of Du Pont Chlorosulfonated polyethylene (CSP), see Cable insulation, p. 21 see Elastomer, p. 22 see Paint, p. 27

Hytrel, trade name of Du Pont PETP copolymer, see Cable insulation, p. 21

H

127

Page 104: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

H HEATING ELEMENT

BASE MATERIAL: Teflon

TYPE: -

SUPPLIER: -

IDENTIFICATION: 291-1980

DESCRIPTION OF MATERIAL: Flexible heating element of total width 68 mm consisting of a carbonized tissue (woven fibres) of width 38 mm embedded in an insulating coating of Teflon

APPLICATION AT CERN: Heating element for vacuum chamber bakeout at the Intersecting Storage Rings and at the Super Proton Synchrotron LSS4 and LSS5

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate 10 Gy/s Doses: 1 X 105, 1 X 106 Gy

METHODS OF TESTING:

RESULTS: Teflon matrix was severely damaged at 1 X 106 Gy. After some handling to test flexibility, the electrical resistance was greater than 2 X 106 n. At the lower dose of 1 X 105 Gy, however, the Teflon did not break, and the electrical resistance was 6.6 X 103 n at a length of 15 cm.

Remarks:

REFERENCES:

APPRECIATION: ***USE IN HIGH LEVEL RAD/A TION AREAS NOT RECOMMENDED*** See Appendix 7

111111111111111111111

101

Dose (Gy)-+

129

Page 105: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

H HF ABSORBER

BASE MATERIAL: Resistive fibres

TYPE: -

SUPPLIER: -

IDENTIFICATION: 150-1974

DESCRIPTION OF MATERIAL: High-frequency (microwave) absorber material composed of rubberized lossy fibres, proposed as anti­reflexion material in RF-accelerating cavity systems. Dimensions: 50 0 X 170 (in mm).

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy Is Doses: 5 X 105

, 1 X 106 Gy

METHODS OF TESTING: Qualitative mechanical test

RESULTS: No damage detected up to 106 Gy

Remarks: Not used because of vacuum problems.

REFERENCES:

APPRECIATION: See Appendix 7

IO' 103

Dose (Gy)-+

no )est ~1 108

131

Page 106: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

H HOSE BASE MATERIAL: Ethylene-propylene rubber (EPR)/glass fibre

TYPE: Flexible insulating water hose

SUPPLIER: Gummi-Maag

IDENTIFICATION: 260-1970

f/f(O) (%1

100

50

OL-~~_L_~~~_j_~~_j_~~_L~~~___L~~~_L_~~__L_~~-~__J__~~-'

132

104

SYMBOL

105

PROPERTY

bursting pressure

107

Dose[Gyl

INITIAL VALUES

11.3 MPa

Page 107: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

H HOSE

BASE MATERIAL: Ethylene-propylene rubber (EPR)/glass fibre

TYPE: Flexible insulating water hose

SUPPLIER: Gummi-Maag

IDENTIFICATION: 260-1970

DESCRIPTION OF MATERIAL: Ethylene-propylene rubber tubes reinforced with flass fibres; diameter: internal 8 mm, external 17 mm

APPLICATION AT CERN: Used for the Intersecting Storage Rings magnet cooling system

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: 5 X 105

, 1 X 106, 2 X 106

, 5 X 106 Gy

METHODS OF TESTING: Bursting pressure tests

RESULTS: Fulfilled specification requirements; no expansion of hoses before bursting

Remarks:

REFERENCES: 36

APPRECIATION: See Appendix 7

103 104 106

Dose (Gy)-+

133

Page 108: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

H HOSE

BASE MATERIAL: EPR/Kevlar fibre

TYPE: Flexible insulating water hose

SUPPLIER: Gummi-Maag

IDENTIFICATION: 261-1980

DESCRIPTION OF MATERIAL: Ethylene-propylene rubber tubes reinforced with Kevlar (aromatic polyamide) fibre. Over-all resistivity higher than 105 n · m. Inner diameters: 8, 13, 19, and 25 mm

APPLICATION AT CERN: Used for Super Proton Synchrotron magnet cooling system. Installed in 1980/81.

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: 1 X 106 Gy

METHODS OF TESTING: Pressure test at 6.4 MPa

RESULTS: No damage; pressure test passed

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

no !est 101

Dose (Gy)-+

___.,

108

135

Page 109: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

H HOSE

BASE MATERIAL: EPR/polyester fibre

TYPE: Flexible insulating water hose

SUPPLIER: Angst & Pfister

IDENTIFICATION: 225-1974

DESCRIPTION OF MATERIAL: Ethylene-propylene rubber tubes reinforced with polyester fibres, inner diameters 8, 13, 19, and 25 mm.

APPLICATION AT CERN: Used for Super Proton Synchrotron water hoses, 197 5 to 1980, and partially also thereafter

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: 1 X 106 Gy

METHODS OF TESTING: Pressure test at 6.4 MP a ( = 4 X operating pressure). Bursting pressure test.

RESULTS: No damage, passed pressure test. Bursting pressure: non-irradiated: 35 MPa

irradiated 1 X 106: 34 MPa.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

101 102 103

Dose (Gy)-+

~o ~es~ ,-+I

137

Page 110: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

H HOSE

BASE MATERIAL: Polyethylene terephthalate (PETP) copolymer

TYPE: -; Hytrel 550

SUPPLIER:

IDENTIFICATION: 226-1974

DESCRIPTION OF MATERIAL: Semi-rigid water hoses made from polyethylene terephthalate (PETP) copolymer (Hytrel), diameter 6 mm, wall thickness 4 mm

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: l X 106 Gy

METHODS OF TESTING: Bursting pressure test

RESULTS: No radiation damage found. Before irradiation the bursting pressure was about 57 X 105 Pa. After irradiation, 57.8 ± 3.6 X 105 Pa were measured.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

Dose (Gy)-.

-+I 108

139

Page 111: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

INS ULA TED WIRE PETP /Poly amide Polyamide-imide Polyester-imide

INSULATING OIL Chlorinated oil Fluorinated oil Mineral oil Silicone oil

INS ULA TING SLEEVE Silicone rubber/glass fibres

Entries and cross-references

see also Thermoshrinking sheath

INSULATING TAPE Paper

Iron

Polyamide paper Polyethylene terephthalate (PETP) PETP I asbestos PETP/epoxy PETP/PETP fibres PETP/polyamide PETP, thermoadhesive Polypropylene see also Adhesive tape

see Magnetic material

I

141

Page 112: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATED WIRE BASE MATERIAL: Polyethylene terephthalate (PETP)/Polyamide; Polyamide-imide resin

TYPE: FI and F2

SUPPLIER: CERCEM

IDENTIFICATION: 240.1-1974

100 r--------....; ·--------·. f/f(O) 1%1

142

50

0 0

SYMBOL

• • ... •

0.5 I.OX 107

Dose[Gyl

PROPERTY INITIAL VALUES

torsion resistance 240 m-• pencil hardness 81.3% torsion resistance 320 m-• pencil hardness 75%

REMARKS

} Type FI

} Type F2

1.5

Page 113: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATED WIRE

BASE MATERIAL: Polyethylene terephthalate (PETP)/Polyamide; Polyamide-imide resin

TYPE: Fl andF2

SUPPLIER: CERCEM

IDENTIFICATION: 240.1-1974

DESCRIPTION OF MATERIAL: Insulated wire for field coils of I kW electric motor. Insulation for type FI is made from PETP with Nylon topcoating; for type F2 from modified amide-imide with topcoat.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: 5 X 106

, l X 107 Gy

METHODS OF TESTING: Elasticity: Twisting together two, 125 mm long, pieces of wire, and noting the number of turns per unit length needed to produce cracks that are visible with the aid of a magnifying glass (Swiss Std. VSM 23780). Hardness: Pencil hardness used to attack the insulation: scale ranging from 68 to 9H in 16 steps (Swiss Std. VSM 23714).

RESULTS: Elasticity: Whereas type 155 showed no change after irradiation, type 170 did so only up to 5 X 106 Gy, but showed cracks after l X 107 Gy. Hardness: Changed one step for type 155; no change for type 170.

Remarks:

REFERENCES: 19

APPRECIATION: See Appendix 7

1111111111 no test

103 108

Dose (Gy)-+

143

Page 114: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATED WIRE BASE MATERIAL: Polyester-imide resin

TYPE: F3

SUPPLIER: CERCEM

IDENTIFICATION: 240.2-1974

f/f(O) [%)

144

1001----------

50

0 0 0.5

SYMBOL PROPERTY

• torsion resistance

• pencil hardness

l.0Xl07 1.5 Dose[Gy]

INITIAL VALVES

400m- 1

94%

Page 115: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INS ULA TED WIRE

BASE MATERIAL: Polyester-imide resin

TYPE: F3

SUPPLIER: CERCEM

IDENTIFICATION: 240.2-1974

DESCRIPTION OF MATERIAL: Insulated wire for field coils of 1 kW electric motor. The insulation is made from polyester-imide resin.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: 5 X 106

, 1 X 107 Gy

METHODS OF TESTING: Elasticity: Twisting together two, 125 mm long, pieces of wire, and noting the number of turns per unit length needed to produce cracks that are visible with the aid of a magnifying glass (Swiss Std. VSM 23780). Hardness: Pencil hardness used to attack the insulation: scale ranging from 6B to 9H in 16 steps (Swiss Std. VSM 23714).

RESULTS: Elasticity: No irradiation effect up to 400 turns/mat 5 X 106 Gy and 320 turns/mat 1 X 107 Gy. Hardness: No irradiation effect at either dose; the high value of 8H (94% of the scale) was retained. No visible alteration up to 1 X 107 Gy.

Remarks:

REFERENCES: 19

APPRECIATION: See Appendix 7

no test

103 107

Dose (Gy)-+

145

Page 116: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING OIL BASE MATERIAL: Chlorinated oil

TYPE: Askarel

SUPPLIER: -

IDENTIFICATION: 52.2-1973

200

f/f(O) [%)

SYMBOL

• • ...

0.5

PROPERTY

breakdown voltage viscosity insulation resistance

I.OX 106

Dose[Gy)

INITIAL VALUES

l8kV/mm 98 mPa· s

8 X 1011 Q/m

For.&, y = -10 log f/fl:O) is plotted (in decibels)

146

1.5

Page 117: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING OIL

BASE MATERIAL: Chlorinated oil

TYPE: Askarel

SUPPLIER:

IDENTIFICATION: 52.2-1973

DESCRIPTION OF MATERIAL: Synthetic oil containing chlorinated diphenyls (Askarel) used as an insulating liquid. Proposed for pulsed magnet insulation; not inflammable.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position EI in air, dose rate 28 Gy/s Doses: 3 X 105

, I X 106 Gy

METHODS OF TESTING: High-voltage breakdown test in a 'Baur'-type set-up with spherical electrodes of 12.5 mm diameter at a distance of 2 mm. Variable voltage supply of 0-150 kV at 40 MO resistance. Steps of 2 kV every minute after 20 min to 2 days rest for each sample. Four samples, three tests per sample. Dynamic viscosity using "Viscotemp Eprecht", t = 20°C.

RESULTS: Breakdown voltage was slightly lower at 3 X 105 Gy. At I X 106 Gy, the sample volume was too small for the test. Viscosity increased by a factor of 2. The dielectric constant decreased from 5. 75 at dose 0 to 5.4 at 106 Gy. The insulation resistance was about I% of the initial value and already rather low at both doses (10 10 O/m). The colour changed from transparent before irradiation to greenish-brown after both irradiation doses. Strong HCl gases evaporated from the irradiated liquid. The chlorine content was 41.9% and decreased after irradiation to about 41. I%.

Remarks: Gas evolution (partly HCl) was 1.3 and 2.6 times the volume of the liquid at the two doses, respectively

REFERENCES: 22

APPRECIATION: ***USE IN RAD/A TJON AREAS NOT RECOMMENDED*** See Appendix 7

I 111111111111111111111111111~ tjo test -+I 104 106 107

Dose (Gy)-+

14 7

Page 118: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING OIL

BASE MATERIAL: Fluorinated oil

TYPE:

SUPPLIER:

IDENTIFICATION: 52.4-1973

DESCRIPTION OF MATERIAL: Synthetic fluorinated oil used as an insulating liquid

APPLICATION AT CERN: Insulation in high-voltage feedthrough of the Super Proton Synchrotron electrostatic septa (LSS2, LSS6)

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 28 Gy/s. Doses: 1 X 106 Gy

METHODS OF TESTING: High-voltage breakdown test in a 'Baur'-type set-up with spherical electrodes of 12.5 mm diameter at a distance of 2 mm. Variable voltage supply of 0-150 kV at 40 MO resistance. Steps of 2 kV every minute after initial rest of 5 min. Ten tests were performed. Dynamic viscosity using "Viscotemp Eprecht", t = 20°c.

RESULTS: Owing to high gas evolution, no tests were possible after irradiation. Before irradiation, the breakdown voltage measured yielded very high values. At the end of a testing series, 62 kV /mm were obtained; whereas at the beginning of a series, 24 kV /mm were measured. Vis­cosity was very low. According to the manufacturer, the liquid will show only minor changes after a dose of 1 X 106 Gy. The measured content of fluorine decreased from 78.6% to 71. 7% at this dose, and some acidity (8 X 10-5

mol/kg) was detected in the liquid. During service in electrostatic septa, about 0.05 mol/kg HF were liberated after a dose of 105 Gy, the acid being neutralized continuously by special equipment.

Remarks: Gas evolution was 10 times the volume of the liquid at the dose 1 X 106 Gy, the gas being very strong and toxic

REFERENCES: 22, 23

APPRECIATION: **"'USE IN RADIATION AREAS NOT RECOMMENDED"'.,.. See Appendix 7

not tsted bec~use of oJtgassing (osses

105

Dose (Gy)-.

149

Page 119: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING OIL BASE MATERIAL: Mineral oil

TYPE: Diala C

SUPPLIER: Shell

IDENTIFICATION: 52.1-1973

f/f(O) [%]

50

SYMBOL

• • ...

0.5

PROPERTY

breakdown voltage dynamic viscosity insulation resistance

·-------- -----·--~~-

I.OX 106

DoselGyl

INITIAL VALUES

22 kV /mm 32mPa·s

3. 7 X 1015 O/m

l.5

For..&.. y = - JO log f/f(O) is plotted (decibels)

150

Page 120: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING OIL

BASE MATERIAL: Mineral oil

TYPE: Di ala C

SUPPLIER: Shell

IDENTIFICATION: 52.1-1973

DESCRIPTION OF MATERIAL: Naphtenic insulating oil, subsequently renamed diala oil b

APPLICATION AT CERN: Insulation and cooling of terminating resistors and of matching boxes of the Super Proton Synchrotron fast pulsed magnets

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30Gy/s Doses: 3 X 105

, 1 X 106 Gy

METHODS OF TESTING: High-voltage breakdown test in a 'Baur'-type set-up with spherical electrodes of 12.5 mm diameter at a distance of 2 mm. Variable voltage supply of 0-150 kV at 40 Mn resistance. Steps of 2 kV every minute after initial rest of 5 min. Ten tests were performed. Dynamic viscosity using "Viscotemp Eprecht", t = 20°c.

RESULTS: Breakdown voltage slightly lowered to 89% and 81 % at both doses. Viscosity increased only about 12%. The dielectric constant decreased by 4% from an initial value of 2.25. The insulation resistance went down by a factor of 1.6 X 10-3

, but the absolute value was still compara­tively high. Colour changed from light yellow at zero dose to dark brown at both doses. No change was noticed in infrared spectra after irradiation; only saturated hydrocarbon bands. No chlorine or free acids were detected.

Remarks: Gas evolution was 2.0 and 5.3 times the volume of the liquid at the two doses, respectively

REFERENCES: 22

APPRECIATION: See Appendix 7

102 10s

Dose (Gy)--+

no ~est -+I 106

151

Page 121: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING OIL BASE MATERIAL: Mineral oil

TYPE: Valvata 460

SUPPLIER: Shell

IDENTIFICATION: 189-1979

f/f(O) 1%1

50

O·~~~'--~~---'~~___JL__~------'-~~~---'--~~___L~~-'--~~-~___[_~~-

103

SYMBOL

152

PROPERTY

dynamic viscosity (24 °C)

106

Dose!Gyl

INITIAL VALVES

l.4Pa·s

Page 122: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING OIL

BASE MATERIAL: Mineral oil

TYPE: Valvata460

SUPPLIER: Shell

IDENTIFICATION: 189-1979

DESCRIPTION OF MATERIAL: A refined mineral oil formerly known as Valvata 79.

APPLICATION AT CERN: Used as insulating oil in the 300 kV and 400 kV plugs for the HY circuits of the electrostatic septa and electrostatic separators in the Super Proton Synchrotron (LSS2, LSS6, LSS5)

IRRADIATION CONDITIONS:

Type: 6°Co gamma source Doses: l X 104

, 5 X 104, 1X105

, 5 X 105, l X 106 Gy,doserate2.8Gy/s

METHODS OF TESTING: Dynamometric viscosity measurement at 24 ° C using concentric cylinders at several speeds

RESULTS: Viscosity decreased about 4% up to 5 X 104 Gy, and then increased again, reaching a value 11% higher than the initial value. Sa!':lples have also been taken after 3 years of operational exposure under high tension. The accumulated dose has been estimated to be about 1 X 105 Gy. In this case, the viscosity increased about 5% (meas­ured at 25 °C), indicating that during operational exposure, only 36% of the dose is needed to get the same damage as in the test.

Remarks:

REFERENCES: 23, 24

APPRECIATION: See Appendix 7

no lest -+I 101 105 108

Dose (Gy)-+

153

Page 123: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING OIL

BASE MATERIAL: Mineral oil

TYPE: -

SUPPLIER:

IDENTIFICATION: 12-1975

DESCRIPTION OF MATERIAL: Used as dielectric and cooling agent in 50 n RF load (Bird model 8408: power 600 W, frequency 0 to 3GHz)

APPLICATION AT CERN: Used for Super Proton Synchrotron accelerating cavities during 19 77-1978

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 5 X 104

, 1 X 105, 5.5 X 105 Gy

METHODS OF TESTING: Static measurement of viscosity using a 'Ubbelonde'-type set-up. Operational test in accelerator.

RESULTS: Up to I X 105 Gy there was almost no change in viscosity; up to 5 X 105 an increase of only 30%. The colour changed from transparent below 5 X 104 Gy to yellow at 5.5 X 105 Gy. Operational test: No difference in RF properties have shown up during the service pericd of 1.5 years. The doses received were rather low.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

no tst .... 1

101 102

Dose (Gy)--+

155

Page 124: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING OIL

BASE MA TE RIAL: Silicone oil

TYPE: DC 200-50

SUPPLIER: Dow Chemical

IDENTIFICATION: 52.3-1973

DESCRIPTION OF MATERIAL: Silicone oil polydimethyl-siloxane used as an insulating liquid, proposed for pulsed magnet insulation. Flash-point temperature above 280°C.

APPLICATION AT CERN: Insulation at the pulse-forming networks of the fast pulsed magnets of the Super Proton Synchrotron (operating voltage 60 kV)

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 28 Gy/s Doses: 3 X 105

, I X 106 Gy

METHODS OF TESTING: High-voltage breakdown test in a 'Baur'-type set-up with spherical electrodes of 12.5 mm diameter at a distance of 2 mm. Variable voltage supply of 0-150 kV at 40 MO resistance. Steps of 2 kV every minute after initial rest of 5 min. Ten tests were performed. Dynamic viscosity using "Viscotemp Eprecht', t = 20°C.

RESULTS: Both the breakdown voltage and the viscosity increased by about 13%; the dielectric constant remained unchanged at 2.5. The insulation resistance was reduced to 33%, but the absolute value was still very high. These values were measured at 5 X 105 Gy. At I X 106 Gy, the liquid had gelatinized and no test was possible. No change noticed in infrared spectra after irradiation. No chlorine or free acids detected.

Remarks: Gas evolution was 3.3 and 4.9 times the volume of the liquid at the two doses, respectively. At I X 106 Gy, the fluid has gelatinized to a gum-type solid. According to supplier, methyl­phenyl siloxane fluids have much better radiation resistance.

REFERENCES: 22

APPRECIATION: ***USE IN RADIATION AREAS NOT RECOMMENDED*** See Appendix 7

•llllllllllllll!lll 101 104 108

Dose (Gy)-+

157

Page 125: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING SLEEVE BASE MATERIAL: Silicone rubber/glass fibres

TYPE: Gl

SUPPLIER: CERCEM

IDENTIFICATION: 182.8- 197 4

f/f(O) (%]

158

100 r-------

50

SYMBOL

• •

" " " ' " '

2.0

PROPERTY

coiling test number of bends

" ' ' ' ' ' ' ' ' " " '

4.0X 106

Dose[Gyl

INITIAL VALUES

100% 100

' ' ' ' 6.0

Page 126: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING SLEEVE

BASE MATERIAL: Silicone rubber/glass fibres

TYPE: GI

SUPPLIER: CERCEM

IDENTIFICATION: 182.8-1974

DESCRIPTION OF MATERIAL: Tubing made from glass-fibre braid coated with silicone rubber, for the insulation of leads in a I kW elec­tric motor

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: I X 106

, 5 X 106 Gy

METHODS OF TESTING: Coiling test, made by winding the tube I 0 times around a core I 0 times its own diameter and noting the defects by inspection with a magnifying glass (Swiss Std. VSM 23 708). Bending test, made by counting the number of 360°backward and forward bends until visible damage occurs (Swiss Std. VSM 23780).

RESULTS: Coiling test:

Bending test 360°:

Colour:

Remarks:

REFERENCES: 19

Before irradiation and after I X 106 Gy no defects were seen. After 5 X 106 Gy, the sample broke immediately. Before irradiation, still no defects after I 00 bends. After I X I 06 Gy, only five bends were necessary before breaking; after 5 X I 06 Gy, breaks occurred immediately. No differences after irradiation.

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

111111111111111111111

10 1 101 J04 JO' 10° 107 JOx

Dose (Gy)--+

159

Page 127: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING SLEEVE BASE MATERIAL: Silicone rubber/glass fibres

TYPE: G2

SUPPLIER: CERCEM

IDENTIFICATION: 182.9-1974

f/f(O) [%]

160

IOOt------

50

SYMBOL

• •

2.0

PROPERTY

coiling test number of bends

4.0X 106

Dose[Gy]

INITIAL VALVES

100% 100

6.0

Page 128: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING SLEEVE

BASE MATERIAL: Silicone rubber/glass fibres

TYPE: G2

SUPPLIER: CERCEM

IDENTIFICATION: 182.9-1974

DESCRIPTION OF MATERIAL: Tubing made from glass-fibre braid coated with silicone rubber, for the insulation ofleads in a 1 kW elec­tric motor

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy/s Doses: 1 X 106

, 5 X 106 Gy

METHODS OF TESTING: Coiling test, made by winding the tube 10 times around a core 10 times its own diameter and noting the defects by inspection with a magnifying glass (Swiss Std. VSM 23 708). Bending test, made by counting the number of 360° backward and forward bends until visible damage occurs (Swiss Std. VSM 23 780).

RESULTS: Coiling test:

Bending test 360°:

Colour:

Remarks:

REFERENCES: 19

Before irradiation and after 1 X 106 Gy no defects were seen. After 5 X I 06 Gy, breaks occurred after one sixth of a turn. Before irradiation, still no defects after 100 bends. After 1 X 106 Gy, only nine bends were necessary before breaking; after 5 X 106 Gy, breaks occurred immediately. Changed from white to grey.

APPRECIATION: See Appendix 7

10' 103 104 105

Dose ( Gy)--+

111111111111111111111

107

161

Page 129: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING TAPE

BASE MATERIAL: Paper

TYPE: -

SUPPLIER: -

IDENTIFICATION: 13.1-1978

DESCRIPTION OF MATERIAL: Insulating paper used as layer insulation for high-voltage transformers, to be impregnated after winding

APPLICATION AT CERN: Transformer inter-winding insulation, used with araldite impregnation

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position EI in air, dose rate 30 Gy/s Doses: 5 X 105

, I X 106, 5 X 106 Gy

METHODS OF TESTING: Qualitative mechanical test

RESULTS: The paper became very brittle after 5 X I 06 Gy

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

IO' 102 104 105

Dose (Gy)--+

lllllllllllllllllllllllll 106 108

163

Page 130: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INS ULA TING TAPE

BASE MATERIAL: Poly amide paper

TYPE: E3;Nomex

SUPPLIER: CERCEM

IDENTIFICATION: 182.3-1974

DESCRIPTION OF MATERIAL: Coil slot insulation made from aromatic polyamide paper composite, for a I kW electric motor

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy/s Doses: 1 X 107 Gy

METHODS OF TESTING: Bending test, counting the number of 360° backward and forward bends (Swiss Std. VSM 23780) on samples of dimensions 100 X 10 mm2

RESULTS: Before irradiation, the material still showed no damage after 100 bends. After a dose of 107 Gy, there was also almost no damage after 100 bends. A sligr.t change in colour was noticed.

Remarks: See also Adhesive tape

REFERENCES: 19

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

105

Dose (Gy)-+

106

no test

165

Page 131: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING TAPE

BASE MATERIAL: Poly amide paper

TYPE: Nomex

SUPPLIER:

IDENTIFICATION: 13.2-1978

DESCRIPTION OF MATERIAL: Aromatic polyamide paper composite (Nomex), used as layer insulation for high-voltage transformers

APPLICATION AT CERN: Transformer inter-winding insulation

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position EI in air, dose rate 30 Gy/s Doses: 5 X 105

, l X 106, 5 X 106 Gy

METHODS OF TESTING: Qualitative mechanical test

RESULTS: No damage detected

Remarks: See also previous entry and Adhesive tape for higher doses

REFERENCES:

APPRECIATION: See Appendix 7

[ __ _.____ _ __.___---L--_ __._ __ ~-~__._n_o_te_sH_l 10 1 103 106 10 7

Dose (Gy)--+

Page 132: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING TAPE

BASE MATERIAL: Polyethylene terephthalate (PETP)

TYPE: EI; Mylar

SUPPLIER: CERCEM

IDENTIFICATION: 182.1-1974

DESCRIPTION OF MATERIAL: Coil slot insulation made from polyethylene terephthalate (Mylar), for a 1 kW electric motor.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position EI in air, dose rate 30 Gy Is Doses: l X 107 Gy

METHODS OF TESTING: Bending test, counting the number of 360° backward and forward bends (Swiss Std. VSM 23 780) on samples of dimensions I 00 X 10 mm 2

RESULTS: Before irradiation, the material still showed no damage after 100 bends. After a dose of 107 Gy, the foil became very brittle and broke before the first complete bend. The colour changed from white to yellow.

Remarks: See also Adhesive tape for lower doses

REFERENCES: 19

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

1111111111111111111111111

101

Dose (Gy)-+

108

169

Page 133: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING TAPE

BASE MATERIAL: Polyethylene terephthalate (PETP)/ Asbestos

TYPE: ES

SUPPLIER: CERCEM

IDENTIFICATION: 252-1974

DESCRIPTION OF MATERIAL: Coil slot insulation made from asbestos bonded by PETP film, for a I kW electric motor

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position EI in air, dose rate 30 Gy/s Doses: I X 107 Gy

METHODS OF TESTING: Bending test, counting the number of 360° backward and forward bends (Swiss Std. VSM 23 780) on samples of dimensions 90 X 20 mm 2

RESULTS: Before irradiation, the material still showed no damage after JOO bends. After a dose of 107 Gy, no major damage was observed.

Remarks:

REFERENCES: 19

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

10 1 102 101 105

Dose (Gy)-.

106

111111111111 no testl

107 108

171

Page 134: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING TAPE

BASE MA TE RIAL: PETP /Epoxy /PETP fibres

TYPE: E6

SUPPLIER: CERCEM

IDENTIFICATION: 182.6-1974

DESCRIPTION OF MATERIAL: Coil slot insulation made from a composite of polyethylene terephthalate (PETP) film and epoxy resin filled with PETP fibres, for a l kW electric motor

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy Is Doses: l X 107 Gy

METHODS OF TESTING: Bending test, counting the number of 360° backward and forward bends (Swiss Std. VSM 23 780) on samples of dimensions 100 X IO mm2

RESULTS: Before irradiation, the material still showed no damage after 100 bends. This material was of compara­tively high strength. After a dose of 107 Gy, it broke before the first complete bend.

Remarks:

REFERENCES: 19

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

no test

103 104

Dose (Gy)-+

173

Page 135: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING TAPE

BASE MATERIAL: PETP/PETP fibres

TYPE: E7

SUPPLIER: CERCEM

IDENTIFICATION: 182.7-1974

DESCRIPTION OF MATERIAL: Coil slot insulation made from a composite of polyethylene terephthalate (PETP) film and PETP fibres, for a l kW electric motor

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: l X 107 Gy

METHODS OF TESTING: Bending test, counting the number of 360° backward and forward bends (Swiss Std. VSM 23780) on samples of dimensions l 00 X l 0 mm 2

RESULTS: Before irradiation, the material showed no damage after l 00 bends. After a dose of 107 Gy, it broke before the first complete bend.

Remarks:

REFERENCES: 19

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

102 103 104 105

Dose (Gy)~

no test

107

175

Page 136: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING TAPE

BASE MATERIAL: PETP/Polyamide

TYPE: E4

SUPPLIER: CERCEM

IDENTIFICATION: 182.4-1974

DESCRIPTION OF MATERIAL: Coil slot insulation made from aromatic polyamide and polyethylene terephthalate composite, for a 1 kW electric motor

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy/s Doses: 1 X 107 Gy

METHODS OF TESTING: Bending test, counting the number of 360° backward and forward bends (Swiss Std. VSM 23 780) on samples of dimensions 100 X 10 mm2

RESULTS: Before irradiation, the material still showed no damage after l 00 bends. After a dose of 107 Gy, there was also no damage after 100 bends. The colour changed.

Remarks:

REFERENCES: 19

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

105

Dose ( Gy)--+

no test

177

Page 137: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING TAPE

BASE MATERIAL: PETP/Polyamide

TYPE: E5

SUPPLIER: CERCEM

IDENTIFICATION: 182.5-1974

DESCRIPTION OF MATERIAL: Coil slot insulation made from aromatic polyarnide and polyethylene terephthalate (PETP) composite with coating, for a I kW electric motor

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position EI in air, dose rate 30 Gy/s Doses: I X 107 Gy

METHODS OF TESTING: Bending test, counting the number of 360° backward and forward bends (Swiss Std. VSM 23780) on samples of dimensions 100 X I 0 mm 2

RESULTS: Before irradiation, the material still showed no damage after 100 bends. After a dose of 107 Gy, the tape broke after 50 bends.

Remarks:

REFERENCES: 19

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

[ __________ ] I() I 101 103 IO' 106

Dose (Gy)--t

llllllllllllln ° t es~ 107 108

179

Page 138: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING TAPE

BASE MATERIAL: Polyethylene terepli.thalate (PETP). thermoadhesi\'e

TYPE: E2; Mylar

SUPPLIER: CERCEM

IDENTIFICATION: 182.2-1974

DESCRIPTION OF MATERIAL: Coil slot insulation, made from polyethylene terephthalate (Mylar) treated to obtain thermoadhesive pro­perties of the tape, for a 1 kW electric motor

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy /s Doses: I X 107 Gy

METHODS OF TESTING: Bending test, counting the number of 360° backward and forward bends (Swiss Std. VSM 23780) on samples of dimensions 100 X 10 mm 2

RESULTS: Before irradiation, the material still showed no damage after 100 bends. After a dose of 107 Gy, the foil became very brittle and broke before the first complete bend. The colour changed from white to yellow.

Remarks: See also Adhesive tape for lower doses

REFERENCES: 19

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

11111111111111111111111111111

10 1

Dose (Gy)-+

181

Page 139: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

I INSULATING TAPE

BASE MATERIAL: Polypropylene (PP)

TYPE: -

SUPPLIER: -

IDENTIFICATION: I 05-1979

DESCRIPTION OF MATERIAL: Tape made of polypropylene (PP) for fixing conductors inside cables of dimensions about I 0 mm wide and less than 0.1 mm thickness

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position EI in air, dose rate 30 Gy/s Doses: 5 X 105

, I X 106, 5 X 106 Gy

METHODS OF TESTING: Bending test

RESULTS: Already at 5 X 105 Gy the material did not withstand one bend. At I X 106 Gy, it easily broke into pieces, and at 5 X 106 Gy, it deteriorated into small flakes.

Remarks: Inside an air-tight cable, the performance of such thin material may be satisfactory.

REFERENCES:

APPRECIATION: ***USE IN RAD/A T!ON AREAS NOT RECOMMENDED*** See Appendix 7

Degradation of mechanical properties:

lllll~ll~llllllllllllllllll 103 106 107

Dose (Gy)-+

183

Page 140: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

JOINT Phenolic paper see also Seal

Entries and cross-references

J

185

Page 141: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

J JOINT, MECHANICAL

BASE MA TERI AL: Phenolic paper

TYPE: Pertinax

SUPPLIER: Leybold Heraeus

IDENTIFICATION: 43.1-1979

DESCRIPTION OF MATERIAL: Ball· bearing cage made from phenolic paper (Pertinax), for a turbopump

APPLICATION AT CERN: To be used in rough vacuum pumping stations in the Super Proton Syrn.:hrotron vacuum system

IRR AD IA TION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: l X 104

, 1 X 105 Gy

METHODS OF TESTING: After irradiation the ball bearing was reassembled and inserted into a pump for operational testing

RESULTS: No damage was detected

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

101 102

1~ 105

Dose (Gy)-+

notes~ ~1 108

187

Page 142: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Kapton, trade name of Du Pont Polyimide, see Adhesive tape

Entries and cross-references

Kevlar, trade name of Du Pont Aromatic poly amide, see Hose

Kynar, trade name of Pennwalt Chemical Corp. Polyvinylidene fluoride, see Thermoshrinking sheath

Materials listed in General Tables in Appendix 5

Kapton, trade name of Du Pont Polyimide, see Cable insulation, p. 2 1

Kel-F, trade name of Minnesota Mining & Manufacturing Co. Polychlorotrifluoroethylene, see Thermoplastic resin, p. 29

K

189

Page 143: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

LIGHTING Polycarbonate Silicone rubber

Lithium polysilicate see Paint

LUBRICATING OIL Diester oil

Luminous paint see Paint

Entries and cross-references

Lupolen, trade name of BASF Polyethylene, see Cable insulation

L

I 9 I

Page 144: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

L LIGHTING

BASE MATERIAL: Polycarbonate; Silicone rubber

TYPE:

SUPPLIER:

IDENTIFICATION: 179-1979

DESCRIPTION OF MATERIAL: Items from a standard neon lamp, as follows: 1) rapid-exchange-type tube sockets made from polycar­bonate (Makrolon); 2) lamp starter St 111; 3) electrical connecting wires, insulated with glass-fibre­reinforced silicone rubber.

APPLICATION AT CERN: Lighting along the passageway in the Super Proton Synchrotron tunnel neutrino cave (SPS-TNC), in­stalled in 1979

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor posbon 35 in air, dose rate approx. 10 Gy/s Doses: 1 X 106 Gy

METHODS OF TESTING: Qualitative mechanical test on items 1 and 3

RESULTS: Item 1: The plastic material Makrolon was more rigid than before irradiation and broke easily when pressure was applied to the plastic attachment spring. Item 2: No te::;ts were made. Glass capsule oflamp starter became dark brown. Item 3: The silicone rubber was very brittle and broke at the smallest mechanical load, leaving the con­ductors naked. The glass-fibre reinforcement remained unchanged.

Remarks: After one year of operation in the SPS-TNC, failure of cables due to shrinkage of the insula­tion (silicone rubber); estimated absorbed dose l X 105 Gy. The cables had to be changed. See also Cable insulations.

REFERENCES:

APPRECIATION: See Appendix 7

•11111111111111111

106

Dose (Gy)-+

193

Page 145: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

L LIGHTING

BASE MA TERI AL: Various

TYPE: 65W

SUPPLIER:

IDENTIFICATION: 176-1977

DESCRIPTION OF MATERIAL: Transistorized power supply unit including a nickel-cadmium accumulator to provide emergency opera­tion in case of mains failure. Complete with standard neon lamp. Specified capacity: I hour operation with mains off.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Accelerator irradiation, CERN Intersecting Storage Rings (ISR-13-102) Doses: 3.5 X 102

, 5 X 103 Gy

METHODS OF TESTING: Irradiation under tension (charging conditions). After irradiation, the most sensitive elements -- the transistors 2N 3 704 and BO I 79 -- were checked in the Electronics Workshop.

RESULTS: After a dose of 3.5 X 102 Gy, the light from the lamp was very feeble and flickering, i.e. there was no igni­tion. The batteries did not hold their charge. After a dose of 5 X 103 Gy, the lamp did not work at all; no light and no battery charge owing to failure of the electronic circuit. The amplification factor of the tran­sistors was already reduced by a factor of 10 after 3.5 X 102 Gy.

Remarks:

REFERENCES: 25

APPRECIATION: ***USE IN RADIATION AREAS NOT RECOMMENDED*** See Appendix 7

10 1 102 10s

Dose (Gy)-+

195

Page 146: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

L LIGHTING BASE MATERIAL: Various

TYPE: -

SUPPLIER: -

IDENTIFICATION: 178-1973

- ---- ----- ---•-----

f/f(O) [%1

196

50

•• .. . ..

OL_~~~~---'--~~~~-'-~~~~~~~~~~L-~~~~-'--~~~~_J

0

SYMBOL

• • .. f(O) = 2.81 V

2.5 DoselkGyl

PROPERTY

battery voltage no load battery voltage charging battery voltage safety operation

2.5 + 24h charging

INITIAL VALUES

2.81 v 2.83 v 2.61 v

Page 147: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

L LIGHTING

BASE MATERIAL: Various

TYPE: -

SUPPLIER: -

IDENTIFICATION: 178-1973

DESCRIPTION OF MATERIAL: Safety lamp with buffered power supply to provide about 30 W for two electric bulbs in case of mains failure, with pilot lamp monitoring, charging during mains supply

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Accelerator irradiation, CERN Intersecting Storage Rings (ISR-13-ID 1), dose rate approx. 2Gy/h

Doses: 2.5 X 103 Gy METHODS OF TESTING:

Measurement of battery voltage for three cases: a) idle; b) charging+ pilot lamp; c) safety operation. Tests were carried out before irradiation, after irradiation and two weeks' rest (no load, no charging), and after 24 h charging after irradiation and rest periods.

RESULTS: No significant damage after a dose of 2.5 X 103 Gy. After the rest period of two weeks, the battery voltage was down 15% but easily recovered, after 24 h charging, to a value only 5% lower than before irradiation.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

no te~t ~1 103 107

Dose (Gy)--+

197

Page 148: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

L LUBRICATING OIL

BASE MATERIAL: Diester oil

TYPE: Aeroshell fluid 12

SUPPLIER: Shell

IDENTIFICATION: 45.2-1974

DESCRIPTION OF MATERIAL: Lubricating oil used for ball bearings in vacuum turbopumps.

APPLICATION AT CERN: Used in 150 rough pumping stations in the Super Proton Synchrotron vacuum system since 1976

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy/s Doses: 3 X 105 Gy

METHODS OF TESTING: Operational testing in the pump

RESULTS: No damage was detected

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

102 104 105

Dose (Gy)-+

notes~ ~1 106 10 7 108

199

Page 149: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASEMATERIAL: Unknown

TYPE: -

SUPPLIER: -

IDENTIFICATION: 45.1-1974

DESCRIPTION OF MATERIAL: Lubricating oil used in vacuum pumping units

APPLICATION AT CERN: The oil was replaced by a more radiation-resistant one

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy/s Doses: 3 X 105 Gy

METHODS OF TESTING:

RESULTS: Viscosity and colour changes (black). Could no longer be used.

Remarks:

REFERENCES:

L LUBRICATING OIL

APPRECIATION: "'**USE IN RAD/A TION AREAS NOT RECOMMENDED*** See Appendix 7

101

Dose (Gy)-+

201

Page 150: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Magnet coil insulation see Thermosetting resin

MAGNETIC MATERIAL Hypermalloy Iron, magnetically soft Iron 3% Si Iron 50%Co Iron 50% Ni

Makrolon, trade name of Bayer Polycarbonate, see Lighting

Entries and cross-references

Micatherm, trade name of Allen Bradley Glass/mica composite, see Switch

Microswitch see Switch

Mineral oil see Insulating oil

MOTOR, ELECTRIC

Mylar, trade name of Du Pont Polyethylene terephthalate, see Adhesive tape see Insulating tape

Melamine-formaldehyde See Paint, p. 27

Materials listed in General Tables in Appendix 5

see Thermosetting resin, p. 30

Mineral oils see Oil, p. 26

Mylar, trade name of Du Pont Polyethylene terephthalate, see G-value, p. 24 see Thermosetting resin, p. 30

M

203

Page 151: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MAGNETIC MATERIAL BASE MATERIAL: Hypermalloy

TYPE: -

SUPPLIER: Unknown

IDENTIFICATION: 244.8-1974

6

t B=f (H) 600

- 4 E

......... <{ 400 -I

2 200

'--~~~--1~~...&-~-"-~~..._~_,_~__.~~...&-~----~___.0

0 I 2 B (T)

non-irradiated; no changes after irradiation to 9 X 1023 n/m2

204

Page 152: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MAGNETIC MATERIAL

BASE MATERIAL: Hypermalioy

TYPE: -

SUPPLIER: Unknown

IDENTIFICATION: 244.8-1974

DESCRIPTION OF MATERIAL: Laminated ring cores of Hypermalioy. Thickness of laminations 0.5 mm. Mylar insulation between layers.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position RG in air; flux 4.3 X 1017 n/m2 s (> 0.1 MeV) Doses: 9 X 1023 n/m 2 (E > 0.1 Me V) Temperature: 150 °C

METHODS OF TESTING: Using a 50 Hz ring core transformer method, hysteresis loops were evaluated on an oscilloscope before and after irradiation, to obtain the following functions:

B = f(H): induction as a function of magnetic field, µ = f(B): permeability as a function of induction, He = f(BR): coercitive force as a function ofremanent induction.

RESULTS: No change in properties after irradiation up to 9 X I 0 19 n/m 2

Remarks: A fluence of 1024 n/m2 (E > 0.1 MeV) corresponds to a dose of 2.2 X 107 Gy in iron or 4 X 109 Gy in organic ( C H2)n materials

REFERENCES: 26

APPRECIATION: See Appendix 7

104 107

Dose (Gy)-+

205

Page 153: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MAGNETIC MATERIAL

BASE MATERIAL: Iron, magnetically soft

TYPE: Fe 99.99%

SUPPLIER:

IDENTIFICATION: 244.11-1974

DESCRIPTION OF MATERIAL: Laminated ring cores of iron (Fe 99.99%). Thickness of laminations 0.5 mm. Mylar insulation between layers.

APPLICATION AT CERN: Core and septa of splitter magnets in the Super Proton Synchrotron

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position RG in air; flux 5.3 X 10 17 n/m 2 s (> 0.1 MeV) Doses: I X 1024 n/m 2 (E > 0.1 MeV) Temperature: 150 °C

METHODS OF TESTING: Using a 50 Hz ring core transformer method, hysteresis loops were evaluated on an oscilloscope before and after irradiation, to obtain the following functions:

B = f(H): induction as a function of magnetic field, µ = f(B): permeability as a function of induction, He = f(BR): coercitive force as a function of remanent induction.

RESULTS: The test did reveal no major change in properties. The permeability was increased by less than I 0%. The test was not appropriate to measure the static properties which govern the service conditions.

Remarks: A fluence of 1024 n/m2 (E > 0.1 MeV) corresponds to a dose of 2.2 X 107 Gy in iron or 4 X 109 Gy in organic (CH 2) 0 materials

REFERENCES: 26

APPRECIATION: See Appendix 7

105

Dose (Gy)--+

108

207

Page 154: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MAGNETIC MATERIAL

BASE MATERIAL: Iron, magnetically soft

TYPE: Low-carbon steel

SUPPLIER:

IDENTIFICATION: 244.20-1974

DESCRIPTION OF MATERIAL: Laminated ring cores of iron. Thickness of laminations 1.5 mm, insulated with Mylar foil of 0.2 mm thickness.

APPLICATION AT CERN: Laminated magnets (quadrupoles and dipoles) in the Super Proton Synchrotron

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position RG in air; flux 5.0 X 1017 n/m 2 s (> 0.1 MeV) Doses: 1 X 1024 n/m 2 (E > 0.1 MeV) Temperature: 150 °C

METHODS OF TESTING: Using a 50 Hz ring core transformer method, hysteresis loops were evaluated on an oscilloscope before and after irradiation, to obtain the following functions:

B = f(H): induction as a function of magnetic field, µ = f(B): permeability as a function of induction, He = f(BR): coercitive force as a function of remanent induction.

RESULTS: The test did reveal no major change in properties. Below 1.8 T, the permeability increased by less than l 0%, and also near 2 Tan increase was noted. However, the test was not appropriate to measure the static properties which govern the service conditions.

Remarks: A fluence of 1024 n/m 2 (E > 0.1 MeV) corresponds to a dose of 2.2 X 107 Gy in iron or 4 X 109 Gy in organic (CH2)n materials

REFERENCES: 26

APPRECIATION: See Appendix 7

10 1 104 105 106 107 108

Dose (Gy)--t

209

Page 155: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MAGNETIC MATERIAL

BASE MATERIAL: Iron, magnetically soft

TYPE: Low-carbon steel

SUPPLIER:

IDENTIFICATION: 244.19-1974

DESCRIPTION OF MATERIAL: Laminated ring cores, cut from 1.5 mm thickness punched and specially annealed C-cores from low­carbon (< 0.1%), low-silicon steel. The heat treatment was at 700-750 °C in reducing atmosphere. The ring cores were not annealed and not insulated.

APPLICATION AT CERN: Used for main magnet cores of the 28 GeV Proton Synchrotron in the year 1957.

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position RG in air; flux 5.4 X 1017 n/m 2 s (> 0.1 MeV) Doses: 1.3 X 1024 n/m 2 (E > 0.1 MeV) Temperature: 150 °C

METHODS OF TESTING: Using a 50 Hz ring core transformer method, hysteresis loops were evaluated on an oscilloscope before and after irradiation, to obtain the following functions:

B = f(H): induction as a function of magnetic field, µ = f(B): permeability as a function of induction, He = f(BR): coercitive force as a function of remanent induction.

RESULTS: The test did reveal no major change in properties. Only above 1.9 T, the permeability µis gradually reduced by 15% at maximum. However, the method of test chosen was not appropriate to measure the static properties governing the service conditions, nor could it detect small changes in the working range B<I.7T.

Remarks: A fluence of 1024 n/m2 (E > 0.1 MeV) corresponds to a dose of 2.2 X 107 Gy in iron or 4 X 109 Gy in organic (CH 2) 0 materials

REFERENCES: 26

APPRECIATION: See Appendix 7

101 102 105 108

Dose (Gy)-+

211

Page 156: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MAGNETIC MATERIAL BASE MATERIAL: Iron. silicon ( 3%)

TYPE: -

SUPPLIER: Unknown

IDENTIFICATION: 244.3-1974

6

t B = f (H ) 600

4 -E ' <! 400 ..........

I

2 200

L--~-L-~_J_~--J~~~-~--L-~--L~~L--~....._~~~__.o

0 I 2 B(T)

non-irradiated

irradiated to 1.0 X I 0 2 ~ n/ rn 2

212

Page 157: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MAGNETIC MATERIAL

BASE MATERIAL: Iron, silicon (3%)

TYPE: -

SUPPLIER: Unknown

IDENTIFICATION: 244.3-1974

DESCRIPTION OF MATERIAL: Laminated ring cores of iron-silicon alloy. Thickness of laminations 0.4 mm. Mylar insulation between layers.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position RG in air; flux 4.8 X 1017 n/m2 s (> 0.1 MeV) Doses: 1 X l0 24 n/m 2 (E > 0.1 MeV) Temperature: 150 °C

METHODS OF TESTING: Using a 50 Hz ring core transformer method, hysteresis loops were evaluated on an oscilloscope before and after irradiation, to obtain the following functions:

B = f(H): induction as a function of magnetic field, µ = f(B): permeability as a function of induction, He = f(BR): coercitive force as a function ofremanent induction.

RESULTS: No major change in properties. See graph on opposite page

Remarks: A fluence of 1024 n/m2 (E > 0.1 MeV) corresponds to a dose of 2.2 X 107 Gy in iron or 4 X 109 Gy in organic (CH2)n materials

REFERENCES: 26

APPRECIATION: See Appendix 7

Dose (Gy)-.

213

Page 158: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MAGNETIC MATERIAL BASE MATERIAL: Iron. cobalt (50%)

TYPE: -

SUPPLIER: Unknown

IDENTIFICATION: 244.14-1974

6

t 600

- 4 E

......... <( 400 -I

2 200

'--~~~~~~~~~~~~~~~~~~~~~~__,O

0 I 2 B (T)

non-irradiated

irradiated to I. I X I OH n/rn 2

214

Page 159: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MAGNETIC MATERIAL

BASE MATERIAL: Iron, cobalt (50%)

TYPE: -

SUPPLIER: Unknown

IDENTIFICATION: 244.14-1974

DESCRIPTION OF MATERIAL: Laminated ring cores of iron-cobalt. Thickness of laminations 0.3 mm. Mylar insulation between layers.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position RG in air; flux 5.3 X 1017 n/m 2 s (> 0.1 MeV) Doses: I.I X 1024 n/m 2 (E > 0.1 MeV) Temperature: 150 °C

METHODS OF TESTING: Using a 50 Hz ring core transformer method, hysteresis loops were evaluated on an oscilloscope before and after irradiation, to obtain the following functions:

B = f(H): induction as a function of magnetic field, µ = f(B): permeability as a function of induction, He = f(BR): coercitive force as a function of remanent induction.

RESULTS: No major change in properties, see graph on opposite page

Remarks: A fluence of 1024 n/m 2 (E > 0.1 MeV) corresponds to a dose of 2.2 X 107 Gy in iron or 4 X 109 Gy in organic (CH2)n materials

REFERENCES: 26

APPRECIATION: See Appendix 7

10 1 103 104 106 107 108

Dose (Gy )--.

215

Page 160: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MAGNETIC MATERIAL BASE MATERIAL: Iron, nickel (50%)

TYPE: -

SUPPLIER: Unknown

IDENTIFICATION: 244.7-1974

103 t fl 800

6

' 11-=f(B), 600 t ~\

\ B=f (H) \ \ - 4 \ E \

......... \ <{ \ 400 - \

\ I \

\

2 200

He= f (Br )

L,_~_L_~,,~f---'~~...J._~--1..~~....._~---L..~-----1'--~~~___..~--:o 0 I 2

B ( T) ....

non-irradiated

irradiated to 1.2 X 1024 n/m 2

216

Page 161: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MAGNETIC MATERIAL

BASEMATERIAL: Iron,nickel(50%)

TYPE: -

SUPPLIER: Unknown

IDENTIFICATION: 244.7-1974

DESCRIPTION OF MATERIAL: Laminated ring cores of iron-nickel. Thickness of laminations 0.3 mm. Mylar insulation between layers.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position RG in air; flux 5.5 X 1017 n/m2 s (> 0.1 MeV) Doses: 1.2 X 1024 n/m 2 (E > 0.1 MeV) Temperature: 150 °C

METHODS OF TESTING: Using a 50 Hz ring core transformer method, hysteresis loops were evaluated on an oscilloscope before and after irradiation, to obtain the following functions:

B = f(H): induction as a function of magnetic field, µ = f(B): permeability as a function of induction, He = f(BR): coercitive force as a function ofremanent induction.

RESULTS: No major change in properties, see graph on opposite page

Remarks: A fluence of 1024 n/m2 (E > 0.1 MeV) corresponds to a dose of 2.2 X 107 Gy in iron or 4 X 109 Gy in organic (CH2) 0 materials

REFERENCES: 26

APPRECIATION: See Appendix 7

101 106 108

Dose (Gy)-+

217

Page 162: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MAGNETIC MATERIAL BASE MATERIAL: Iron. nickel (50%)

TYPE: -

SUPPLIER: Unknown

IDENTIFICATION: 244.4-1974

1d~~----~-,--~~~-------~---tµ

800 6

I

t I 600 I

I B=f(H) I - 4 I

E I ......... I

<! I

I 400 - I

I

2 .,~"'" 200

" ,?(=f(B l , c r

---- 0 0 I 2

B ( T) ~

non-irradiated

irradiated to 8 X 1023 n/m 2

218

Page 163: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MAGNETIC MATERIAL

BASE MATERIAL: Iron, nickel (50%)

TYPE: -

SUPPLIER: Unknown

IDENTIFICATION: 244.4-1974

DESCRIPTION OF MATERIAL: Laminated ring cores of iron-nickel. Thickness of laminations 0.3 mm. Mylar insulation between layers.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position RG in air; flux 3.8 X 1017 n/m 2 s (> 0.1 MeV) Doses: 8 X 1023 n/m 2 (E > 0.1 MeV) Temperature: 150 °C

METHODS OF TESTING: Using a 50 Hz ring core transformer method, hysteresis loops were evaluated on an oscilloscope before and after irradiation, to obtain the following functions:

B = f(H): induction as a function of magnetic field, µ = f(B): permeability as a function of induction, He = f(BR): coercitive force as a function of remanent induction.

RESULTS: No major change in properties, see graph on opposite page

Remarks: A fluence of 1024 n/m2 (E > 0.1 MeV) corresponds to a dose of 2.2 X 107 Gy in iron or 4 X 109 Gy in organic (CH 2)n materials

REFERENCES: 26

APPRECIATION: See Appendix 7

102 106

Dose (Gy)-+

219

Page 164: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MOTOR, ELECTRIC

BASE MATERIAL: Various

TYPE: GR 32.0

SUPPLIER: ITT

IDENTIFICATION: 285-1980

DESCRIPTION OF MATERIAL: Motor with built-in speed reducer. Radiation-sensitive items: Phenolic resin (rotor support), polyamide, epoxy resins.

APPLICATION AT CERN: Used in electrostatic septa in the Super Proton Synchrotron LSS5

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-ofTreractor position 35 in air, dose rate 10 Gy/s Doses: 1 X 106 Gy

METHODS OF TESTING: Operational test

RESULTS: Slight degradation of support of commutator brushes. No change in electrical properties, working well.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

no ~est ---.1 101 104

Dose (Gy)-+

221

Page 165: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MOTOR BASEMATERIAL: Various

TYPE: AXEM F9M4 with gears E90

SUPPLIER: CEM

IDENTIFICATION: 2 70-19 7 5

Results of manufacturer's check after irradiation

222

Tested property

Measured electromotive force at 16. 7 s-'

Measured torque at 0, 16. 7 s- 1• 33.3 s- 1

and 50 s- 1

Insulation test

Mechanical test on bond of magnets

Mechanical test on bond of rotor

Mechanical test on ball bearing

Lubrilication grease of stepping down gears

Colour of insulation of rotor and magnets

Result of test

Reduction of 3% within error

Within + 6/-8% of initial value (within error)

Good at 350 V

Good

Good

Good

Seems good

Slightly brownish

Page 166: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MOTOR

BASE MATERIAL: Various

TYPE: AXEM F9M4 with gears E90

SUPPLIER: CEM

IDENTIFICATION: 270-1975

DESCRIPTION OF MATERIAL: Servomotor with disk-type rotor, 55 W /24 d.c., with reduction 1/75 delivering 12. 7 Nm at 0.67 s- 1

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: 6°Co source, dose rate 3 Gy/s Doses: 1 X 106 Gy

METHODS OF TESTING: Mechanical and electrical tests before and after irradiation performed by the supplier

RESULTS: No change of mechanical or electrical properties within measurement error. Slight change in colour of ad­hesive and insulation resins noticed.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

101 105

Dose (Gy)-+

no jest ~1 106 108

223

Page 167: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MOTOR, ELECTRIC BASE MATERIAL: Various, see table

TYPE: MEUA 90S4. COMPAX

SUPPLIER: CEM

IDENTIFICATION: 181-1975

Results ofinsulation tests on windings

5 kV dry insulation resistance: greater than 20 GQ. Tampon moistened with salty water, 5 kV: only one feeble point found.

224

Breakdown voltage at 50 Hz: minimum 3.9 kV, more than twice the specified value.

Check on radiation effects in the especially selected radiation-resistant components (after disassembly of motor)

Functional item

Coil impregnation

Wire insulation

Coil slot insulation

Interphase insulation

Cable insulation

Insulating sleeve

Filler

Terminal board

Fan

Lubricating grease

Selected material, brand name

Norsodyne 292T: tetrahydrophthalic polyester

Port a Bin son type IV: resin ester-imide

Nomex: aromatic polyamide/paper

Thernomid E40NC: aromatic polyamide/PETP

Neoprene

Couzin453: glass fibre/ silicone

Tergal fibres, impregnated

Charged polyester

Poly amide A4K

APL 700

Results

No visible cracks; no change of colour; no other change

Resists coiling and uncoiling test on core 4 X dia.

Good resistance to tearing and 'bending en bloc·

Good resistance to 'bending en bloc'

Breaks in coiling test on core IO X dia. Sufficient for service conditions

Still soft

Good resin impregnation, compact

Perfect

Colour deep yellow. Still soft enough.

Some leakage, but the lubricant did not become detached. Still homogeneous.

Page 168: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Various, see table on opposite page

TYPE: MEUA 90S4, COMPAX

SUPPLIER: CEM

IDENTIFICATION: 181-1975

DESCRIPTION OF MATERIAL:

M MOTOR, ELECTRIC

Motor COMPAX 1.1 kW, 220/380 V triple phase. Prototype with selected constituents according to irradiation tests (Ref. 19) (see table) to obtain operation up to 106 Gy.

APPLICATION AT CERN: Installed in the Super Proton Synchrotron for adjustment of beam transport elements and for moving beam dumps.

IRRADIATION CONDITIONS:

Type: 6°Co source, dose rate approx. 1 Gy/s Doses: 106 Gy

METHODS OF TESTING: After homogeneous irradiation under tension (no load, free running), the motor was tested and then dis­assembled by the research laboratories of the supplier, to judge the damage to the different constituents.

RESULTS: Apart from a slight deterioration of the insulation of the fixed leads and a slight coloration of the plastic parts, no changes were detected after disassembly. Results of insulation tests were well superior to those given in the specification. For detailed results, see table on opposite page.

Remarks:

REFERENCES: 19

APPRECIATION: See Appendix 7

no }est -+I 101 102 105 108

Dose (Gy)~

225

Page 169: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MOTOR, ELECTRIC BASE MATERIAL: Various. see table

TYPE: MEFA 90L8

SUPPLIER: CEM

IDENTIFICATION: 262-1975

Description of material

Wire insulation: Ester-imide resin. Port a Binson, type IV

Slot and phase insulation: Nomex (aromatic polyamide paper)

Cable insulation: Kapton + silicone-impregnated glass-fibre braid

Insulating sleeves: Kapton tape

Impregnation: Norsodyne 292 T (polyester resin)

Terminal board: none

Lubricant: Chevron NRRG 235

Fan: Suppressed

226

Page 170: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MOTOR, ELECTRIC

BASE MATERIAL: Various, see table on opposite page

TYPE: MEF A 90L8

SUPPLIER: CEM

IDENTIFICATION: 262-1975

DESCRIPTION OF MATERIAL: Asynchronous motor, triple phase, 220/380 V, I. I kW at 750 r/min. Designed operation time 5 min/h. For a further description of materials, see table on opposite page.

APPLICATION AT CERN: Used for adjustment and remote handling of beam transport elements in the Super Proton Synchrotron neutrino beam facility

IRRADIATION CONDITIONS:

Type: 6°Co source, dose rate 2 Gy/s Doses: I X 107

, 3 X 107 Gy

METHODS OF TESTING: Insulation resistance and high-voltage tests (I, 2, 3, and 4 kV) between phase windings and winding to cage. Thereafter operation under intermittent load for 24 hours.

RESULTS: No defects found, still operating according to specifications

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

101 104 10s

Dose (Gy)-+

lllllllllno testj 108

227

Page 171: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

M MOTOR, ELECTRIC BASE MATERIAL: Various. see table

TYPE: MT l 00, LB 28, F 215-8

SUPPLIER: ASEA

IDENTIFICATION: 263-1975

Description of material

Wire insulation: Polyimide

Slot and phase insulation: Kapton

Cable insulation: Kapton + silicone-impregnated glass-fibre braid

Insulating sleeves: Epoxy resin with glass-fibre braid

Coil impregnation: Araldite F (CY205 + HY905)

Terminal board: Steatit

Fan: Aluminium

Lubricant: Chevron NRRG

Corrosion protection: Zinc chromate

228

Page 172: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Various, see table on opposite page

TYPE: MT 100, LB 28, F 215-8

SUPPLIER: ASEA

IDENTIFICATION: 263-1975

DESCRIPTION OF MATERIAL:

M MOTOR, ELECTRIC

Asynchronous motor, triple phase, 380 V, 1.1 kW at 700 r/min. Designed operation time 2 min/h. For a further description of materials, see table on opposite page. Proposed for moving beam transport ele­ments in the Super Proton Synchrotron.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: 6°Co source, dose rate 2 Gy/s Doses: 1 X 107

, 2 X 107, 3 X 107 Gy

METHODS OF TESTING: Operation under intermittent load for 24 hours. Insulation resistance and high-voltage tests (1, 2, 3, and 4 kV) between phase windings and winding to cage.

RESULTS: Still operating according to specifications. Breakdown during the last 4 kV test.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

104 105

Dose (Gy)-+

llllllllno tes~ 108

229

Page 173: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Entries and cross-references

Neoprene Chloroprene rubber, see Cable insulations

Nitrile-butadiene rubber (NBR) see Seal

Nomex, trade name of Du Pont Polyamide paper, see Adhesive tape see Insulating tape

Noryl, trade name of General Electric Polyphenylene oxide, see Connector

Novo lac

Nylon

see Thermosetting resin

Polyamide, see Cable tie see Adhesive tape see Insulating tape see Vacuum valve

Materials listed in General Tables in Appendix 5

Neoprene Polychloroprene rubber see Cable insulation, p. 21 see Elastomer, p. 22 see G-value, p. 24 see Hose, p. 25 see Paint, p. 2 7

Nomex, trade name of Du Pont

Nylon

Aromatic polyamide, see Textile, p. 28

Polyamide, see G-value, p. 24 see Hoses, p. 25 see Textile, p. 28 see Thermoplastic resin, p. 29

N

231

Page 174: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Entries and cross-references

Oil Table of general relative radiation effects in Appendix 5 see Insulating oil see Lubricating oil

OPTICAL FIBRE Glass Glass/B, Ge, Sb, Pb Glass/Ge Silica/F

0-ring see Seal

Materials listed in General Tables in Appendix 5

Orlon, trade name of Du Pont Polyacryl, see Textile, p. 28

0

233

Page 175: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Glass

TYPE: -

SUPPLIER: -

IDENTIFICATION: 142-1979

DESCRIPTION OF MATERIAL: Two fibre-optic faceplate disks of thickness 5 mm and 7.5 mm

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Accelerator CERN Intersecting Storage Rings (ISR-I3-ID2) Doses: 2 X 102 Gy

METHODS OF TESTING:

0 OPTICAL FIBRE

Transmission measurement by manufacturer using a densicron and collimated white light

RESULTS: The light transmission was 65% and 60% for the 5 mm and 7.5 mm plates, respectively, before irradia­tion. After a dose of 2 X 102 Gy, the transmission decreased about 8%, yielding 60% and 55%.

Remarks:

REFERENCES: 17

APPRECIATION: See Appendix 7

I+- -.I Dose (Gy)-+

235

Page 176: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

236

0 OPTICAL FIBRE

BASE MATERIAL: Glass B. Ge. Sb. Pb

TYPE: SCT 345. SCT 350. SCT 368. SCT426

SUPPLIER: Schott & Gen.

IDENTIFICATION: 1.3-1978

100

f-f(O) {dB/km I

50

0 0

SYMBOL

~} ~}

0.5

PROPERTY

attenuation at 850 nm

attenuation at 1080 nm

DoselGyl I.OX 102

INITIAL VALVES

6.7 dB/km 3.9 dB/km 8.1 dB/km 4.2 dB/km

3.6dB/km 2.2 dB/km 6.0dB/km 2.2 dB/km

t:,,

1.5

REMARKS

SCT 345 SCT 350 SCT 368 SCT 426

SCT 345 SCT 350 SCT 368 SCT 426

Page 177: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

0 OPTICAL FIBRE

BASE MATERIAL: Glass B, Ge, Sb, Pb

TYPE: SCT 345, SCT 350, SCT 368, SCT 426

SUPPLIER: Schott & Gen.

IDENTIFICATION: 1.3-1978

DESCRIPTION OF MATERIAL: Gradient fibres made from glass (Si02, B20J), as follows: SCT 345 (Doped with GeO) Core diam. 49 µm Ext. diam. l30µm SCT350 GeO,Sb) 40µm 137 µm SCT 368 Sb) 42µm 135µm SCT 426 Pb20~) 56µm l35µm

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Accelerator CERN Intersecting Storage Rings (ISR-I3-ID2) Doses: 1.5 X 102 Gy

METHODS OF TESTING: Attenuation and pulse dispersion at 850 and 1080 nm measured by manufacturer

RESULTS: After 1.5 X 102 Gy, the attenuation had increased by 25 to 46 dB/km, or 300 to 40,000 times on a linear scale for the operational wavelength of 850 nm. At 1080 nm, for which wavelength the fibres were not designed, the attenuation after irradiation of types 368 and 426 increased by only 8 and 7 dB/km, res­pectively.

Remarks:

REFERENCES: 27

APPRECIATION: ***USE IN RAD/A TION AREAS NOT RECOMMENDED*** See Appendix 7

101

Dose (Gy)-t

237

Page 178: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

0 OPTICAL FIBRE BASE MATERIAL: Glass/Ge

TYPE: A TF 1 72

SUPPLIER: AEG-Telefunken

IDENTIFICATION: 1.1-1978

200

f/f(O) 1%1

238

100

SYMBOL

• •

0.5 DoselGy]

PROPERTY

attenuation at 850 nm attenuation at 1080 nm

l.OX !OJ

INITIAL VALUES

5.2 dB/km 4.3 dB/km

1.5

Page 179: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

0 OPTICAL FIBRE

BASE MATERIAL: Glass/Ge

TYPE: A TF 1 72

SUPPLIER: AEG-Telefunken

IDENTIFICATION: 1.1-1978

DESCRIPTION OF MATERIAL: Gradient fibre, mainly Ge doped. Attenuation 5.2 dB/km at 860 nm, core diameter 44 µm, external diame­ter 128µm.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Accelerator CERN Intersecting Storage Rings (ISR-13-ID 1) Doses: 5 X 102

, 1 X 103 Gy

METHODS OF TESTING: Measurement of attenuation at 850 and 1080 nm by the manufacturer

RESULTS: After 5 X 102 Gy, the attenuation had already increased by 145 dB/km making the fibre totally useless at the operation wavelength of 850 nm. Extrapolated value at 1.5 X 102 Gy: increase of 43 dB/km. However, at 1080 nm the attenuation was only 10 dB/km after 5 X l 02 Gy or 5 dB/km at 1.5 X 102 Gy, leaving the fibre still useful at this wavelength.

Remarks:

REFERENCES: 27

APPRECIATION: ***USE IN RAD/A TION AREAS NOT RECOMMENDED*** See Appendix 7

Dose ( Gy) --+

239

Page 180: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

0 OPTICAL FIBRE BASE MATERIAL: Silica/F

TYPE: HQS067, HQS 100

SUPPLIER: Heraeus Quarzschmelze

IDENTIFICATION: 1.2-1978

f-f(O) [dB/km I

SYMBOL

• } • ... } •

240

0.5

PROPERTY

attenuation at 850 nm

attenuation at 1080 nm

l.OX 102 l.5 Dose[Gyl

INITIAL VALUES REMARKS

3.8 dB/km HQS067 3.6dB/km HQS 100 1.5 dB/km HQS067 1.8 dB/km HQS 100

Page 181: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Silica/F

TYPE: HQS 067, HQS 100

SUPPLIER: Heraeus Quarzschmelze

IDENTIFICATION: 1.2-1978

DESCRIPTION OF MATERIAL: Type

HQS 067, step profile HQS 100, gradient fibre

APPLICATION AT CERN:

i.d. (um)

100 45

IRRADIATION CONDITIONS:

o.d. Base material (.um)

125 Si02 pure 125 Si0 2 pure

Doping

3%F max. 3% F

Type: Accelerator CERN Intersecting Storage Rings (ISR-I3-ID2) Doses: 1.5 X 102 Gy

METHODS OF TESTING: Attenuation at 860 and 1060 nm measured by manufacturer

RESULTS:

0 OPTICAL FIBRE

Attenuation

3.8 dB/km (860 nm) 3.6 dB/km (860 nm)

After 1.5 X 102 Gy, the attenuation had increased by 39 and 106 dB/km, or 8 X 103 and 4 X 1010 times on a linear scale for the operational wavelength of 860 nm. At l 060 nm, the increase in attenuation was 19 and 29 dB/km, respectively.

Remarks:

REFERENCES: 27

APPRECIATION: "'**USE IN RAD/A TION AREAS NOT RECOMMENDED*** See Appendix 7

Dose (Gy)--+ 241

Page 182: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Entries and cross-references

PAINT Table of general relative radiation effects in Appendix 5 Acrylic resin, luminescent pigment Epoxy resin Lithium polysilicate Poly acrylate Polyurethane

Paper see Insulating tape

Particle detector see Silicon detector

Pertinax, trade name of Felten & Guillaume Phenolic paper, see Joint

Plexiglas, trade name of Roehm & Haas Polyacryl, see Scintillator

Poly acrylate see Paint see Scintillator

Polyamide see Adhesive tape see Cable tie see Insulated wire see Insulating tape see Vacuum valve

Polybutylene terephthalate (PBTP) see Cable tie

Polycarbonate see Lighting

Polychloroprene (Neoprene) see Cable insulation see Seal

Polyester resin see Insulated wire see Terminal board see also Polyethylene terephthalate

Polyethylene (PE) and (XLPE) see Cable insulation see Cable tie

Polyethylene terephthalate (PETP) see Adhesive tape see Hose see Insulated wire see Insulating tape

p

243

Page 183: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

p Polyhydantoin

see Adhseive tape

Polyimide see Adhesive tape

Polyolefin see Cable insulation see Thermoshrinking sheath

Polyphenylene oxide (PPO) see Connector

Polyphenylene sulfide (PPS) see Connector

Polypropylene (PP) see Insulating tape

Polysiloxane see Silicone rubber

Polytetrafluoroethylene (Teflon PTFE) see Heating element

Polyurethane resin (PUR) see Paint see Foam

Polyurethane rubber (PUR) see Seal

Polyvinylidene fluoride see Thermoshrinking sheath

Polyvinyl chloride (PVC) see Cable insulation

Polyvinyl toluene see Scintillator

244

Page 184: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Materials listed in General Tables in Appendix 5

Perbunan, trade name of Bayer Acrylonitrile-butadiene rubber, see Hose, p. 25

Perfluoro(ethylene/propylene) (FEP) see Cable insulation, p. 21 see Thermoplastic resin, p. 29

Phenolic resin see Thermosetting resin, p. 2 7 see Paint, p. 30

Phosphate oil see Oil, p. 26

Polyacryl see Textile, p. 28

Polyacrylonitrile see G-value, p. 24

Polyamide (Nylon) see G-value, p. 24 see Hose, p. 25 see Textile, p. 28 see Thermoplastic resin, p. 29

Polybutadiene see G-value, p. 24

Polycarbonate see Thermoplastic resin, p. 29

Polychloroprene (Neoprene) see Cable insulation, p. 21 see Elastomer, p. 22 see G-value, p. 24 see Hose, p. 25 see Paint. p. 2 7

Polychlorotrifl uoroethylene (PCTFE) see Thermoplastic resin, p. 29

Polyester see Paint, p. 27 see Textile, p. 28 see Thermosetting resin, p. 30

Polyethylene (PE) and (XLPE) see Cable insulation, p. 21 see G-value, p. 24 see Hose, p. 25 see Thermoplastic resin, p. 29

p

245

Page 185: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

p Polyethylene terephthalate (PETP)

see Cable insulation, p. 21 see G-value, p. 24 see Thermosetting resin. p. 30

Polyglycol oil see Oil, p. 26

Polyimide see Cable insulation, p. 21

Polyisobutylene see G-value, p. 24

Polymethyl methacrylate (PMMA) see G-value, p. 24 see Paint, p. 27 see Thermoplastic resin, p. 29

Polyolefin see Cable insulation, p. 21 see Hose, p. 25

Polyphenylene oxide (PPO) see Hose, p. 25

Polypropylene (PP) see Cable insulation, p. 21 see Thermoplastic resin, p. 29

Polysiloxane (Silicone rubber, SIR) see Cable insulation, p. 21 see Elastomer, p. 22 see G-value, p. 24 see Hose, p. 25

Polystyrene see G-value, p. 24 see Thermoplastic resin, p. 29

Polytetrafluoroethylene (Teflon PTFE) see Cable insulation, p. 21 see G-value, p. 24 see Hose, p. 25 see Thermoplastic resin, p. 29

Polyurethane resin (PUR) see Paint, p. 27 see Thermosetting resin, p. 30

Polyurethane rubber (PUR)

246

see Cable insulation, p. 21 see Elastomer, p. 22 see G-value, p. 24

Page 186: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Polyvinyl alcohol see G-value, p. 24

Polyvinyl butyral see Thermoplastic resin, p. 29

Polyvinyl chloride (PVC) see Cable insulation, p. 21 see G-value, p. 24 see Hose, p. 25 see Thermoplastic resin, p. 29

Polyvinyl formal see Thermoplastic resin, p. 29

Polyvinylidene chloride see Textile, p. 28 see Thermoplastic resin, p. 29

Pyrofil, trade name ofDaetwyler Ethylene-propylene rubber, see Cable insulation, p. 21

p

247

Page 187: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

p PAINT

BASE MATERIAL: Acrylic resin, luminescent pigment

TYPE: -

SUPPLIER: -

IDENTIFICATION: 267-1978

DESCRIPTION OF MATERIAL: Luminous paint glowing green in the dark, used for warning signs. Special luminescent pigment bonded with pure acrylic resin, no radioactive doping element. According to manufacturer, 8% of initial luminosi­ty retained after 30 min.

APPLICATION AT CERN: Used in Super Proton Synchrotron underground tunnels as indication signs in case of power cut.

IRRADIATION CONDITIONS:

Type: Accelerator, in the CERN Super Proton Synchrotron tunnel neutrino cave Doses: 1.5 X 105 Gy

METHODS OF TESTING: Paint applied on cardboard strips of 5 X 20 X 200 mm 3

Visual check of glow effect.

RESULTS: No damage was detected

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

Dose (Gy)-+

no }est

106

~1 108

249

Page 188: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

p PAINT BASE MATERIAL: Epoxy resins

TYPE: Epikote

SUPPLIER: Dr. w. Mader AG

IDENTIFICATION: 247.1-1973

Impact Grid

Material Dose scarifi- IHVh1 Visual judgement hardness cation••

(Gy) SNVl37112 SNVl37111

Epoxy two-component coating. 0 135 0 White, silky, glossy Epikotetype 1001 hardened 5 x 105 127 0 900 Slight colour change in situ with a solvent containing IX 106 151 0 900 Important colour change aliphatic amine adduct. 5 x 106 124 3 1200 Brown, film disintegrated

Epoxy two-component coating. 0 140 4 White. glossy Epikote type 1009 hardened 5 x 105 145 4 530 } Slight colour change with a solvent containing IX 106 154 4 480 aromatic diisocyanate. 5 x 106 135 4 300 Colour changed to yellow

Epoxy two-component laminate. 0 154 4 Reddish brown Epikote type 828. hardened with 5 x 105 156 4 430 Unchanged a solvent-free aromatic amine. IX 106 149 4 700 Slight colour change

5 x 106 153 4 600 Important colour change

a) Appreciation: 0 = very good, I = good, 2 = moderate to good, 3 = moderate, 4 = bad bl IHV =Infinitesimal hardness before film swelling in steam.

250

Page 189: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Epoxy resins

TYPE: Epikote

SUPPLIER: Dr. W. Mader AG

IDENTIFICATION: 247.1-1973

DESCRIPTION OF MATERIAL: Epoxy two-component coating. Epikote type, hardened with aromatic and aliphatic amines

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 5 X 105, 1 X 106

, 5 X 106 Gy

METHODS OF TESTING: Impact hardness, grid scarification, infinitesimal hardness, and visual judgement

RESULTS: See table on opposite page

Remarks:

REFERENCES: 28

APPRECIATION: See Appendix 7

no }est

Dose (Gy)-.

p PAINT

~1

251

Page 190: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

p PAINT BASE MATERIAL: Epoxy and lithium polysilicate resins

TYPE: See table

SUPPLIER: Dr. w. Mader AG

IDENTIFICATION: 246-1972

Impact Grid Material Dose sacrifi- Visual judgement hardness

cation'1

(Gy) SNV 137112 SNV 137111

Epoxy two-component coating, 0 190-196 2 White, glossy Novolac type, hardened with a 5 x 106 203-206 3 } Spotted, slight colour change solvent containing aromatic 8 x 106 177-170 4 amine. 2 x 107 183-192 4 Partial detachment of layers

Epoxy two-component coating, 0 139-135 I Grey, glossy Epikote type I 00 I, hardened 5 x 106 131-135 0 Unchanged in situ with a solvent containing 8 x 106 } Spotted. slight colour change. aliphatic amine adduct. 2 x 107 partial detachment of layers

Epoxy two-component laminate, 0 202-214 3-4 Reddish brown, glossy Epikote type 828, hardened with 5 x 106 207-211 3-4 Slight colour change a solvent-free aromatic amine. 8 x 106 } Important colour change,

2 x 107 most parts detached

Lithium polysilicate/zinc- 0 123-140 0-1 Grey dust paint, diluted with water. 5 x 106 116-124 I Unchanged

8 x 106 111-117 I Unchanged

a) Appreciation: 0 = very good, I = good, 2 = moderate to good. 3 = moderate, 4 = bad

252

Page 191: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

p PAINT

BASE MATERIAL: Epoxy and lithium polysilicate resins

TYPE: See table on opposite page

SUPPLIER: Dr. w. Mader AG

IDENTIFICATION: 246-1972

DESCRIPTION OF MATERIAL: Epoxy-type two-component coatings hardened with aromatic or aliphatic amines. Lithium polysilicate/ zinc-dust paint

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 5 X 105

, 8 X 106, 2 X 107 Gy

METHODS OF TESTING: Impact hardness, grid scarification test, and visual judgement

RESULTS: See table on opposite page

Remarks:

REFERENCES: 28

APPRECIATION: See Appendix 7

Dose (Gy)--+

253

Page 192: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

p PAINT BASE MATERIAL: Epoxy. polyacrylate. and polyurethane resins

TYPE: See table

SUPPLIER: Dr. W. Mader AG

IDENTIFICATION: 245-1973

Grid Material Dose scarifi- IHVb1 Visual judgement

cation a> (Gy) SYN 137111

2 X epoxy primer hardened with 0 0 490 White, glossy aromatic diisocyanate. 3 x 106 0 430 } Very little colour change 2 X PUR topcoat hardened with 5 x 106 0 280 aliphatic diisocyanate. 1 X 107 0 313 Little colour change

1 X ethyl silicate/zinc dust primer. 0 1 200 White, glossy 1 X epoxy primer hardened with 3 x 106 3 333 } Very little colour change aromatic diisocyanate. 5 x 106 0 475 2 X polyacrylate topcoat con- 1 X 107 2-3 425 Little colour change taining a hydroxyl group, hardened with aliphatic diisocyanate.

2 X epoxy primer hardened with 0 0 320 White, glossy polyamino amide. 3 x 106 0 345 } Colour changed to yellow 2 X epoxy topcoat hardened with 5 x 106 0 185 aromatic diisocyanate. IX 107 0 280 Colour changed to dark yellow

2 X epoxy primer hardened with 0 0 275 White, glossy polyamine adduct. 3 x 106 0 245 } Slight colour change to yellow 2 X epoxy topcoat hardened with 5 x 106 0 270 aromatic amine, low solvent content. 1X107 0-1 250 Colour changed to yellow

3 X epoxy laminate hardened with 0 0 275 Grey aromatic amine, low solvent content. 3 x 106 0 250 } Colour changed to brown

5 x 106 0 210 1 X 107 0 190 Colour changed to dark brown

a) Appreciation: 0 = very good. I = good. 2 = moderate to good. 3 = moderate, 4 = bad b) IHV = Infinitesimal hardness before film swelling in steam.

254

Page 193: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

p PAINT

BASE MATERIAL: Epoxy, polyacrylatc, and polyurethane resins

TYPE: See table on opposite page

SUPPLIER: Dr. W. Mader AG

IDENTIFICATION: 245-1973

DESCRIPTION OF MATERIAL: Complete coating systems essentially based on expoxy resins with corrosion protection primer and top­coat

APPLICATION AT CERN: Super Proton Synchrotron beam dump coatings

IRRADIATION CONDITIONS:

Type: Accelerator, CERN Proton Synchrotron, targets l and 8 Doses: 3 X 106

, 5 X 106, l X 107 Gy

METHODS OF TESTING: Grid scarification, infinitesimal hardness, and visual judgement

RESULTS: Apart from colour changes, no important alterations were seen; see table on opposite page

Remarks:

REFERENCES: 28

APPRECIATION: See Appendix 7

no test

101 102 10 1 104 106 107

Dose (Gy)--t

255

Page 194: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

p PAINT BASE MATERIAL: Polyurethane resins

TYPE: See table

SUPPLIER: Dr. W. Mader AG

IDENTIFICATION: 247.2-1973

Impact Grid

Material Dose scarifi- IHV 01 Visual judgement hardness

cation•1

(Gy) SNV 137112 SNV137111

Polyurethane two-component 0 141-145 0 White, glossy coating hardened with a solvent 5 x 106 172-175 2-3 Colour change containing aromatic diisocyanate. 8 x 106 Important colour change

2 x 107 Formation of bubbles

Polyurethane two-component 0 163 4 White, glossy coating hardened with a solvent 5 x 10~ 165 4 Unchanged containing aliphatic diisocyanate. IX 106 174 4 } Slight colour change

5 x 106 162 4

Polyurethane two-component 0 165 4 White, glossy coating with polyvinyl butyrate 5 X 101 168 4 450 wash primer hardened with a solvent IX 106 172 4 425 containing aliphatic diisocyanate. 5 x 106 166 4 300

a) Appreciation: 0 = very good, l = good, 2 = moderate to good, 3 = moderate, 4 = bad b) IHV = Infinitesimal hardness before film swelling in steam.

256

Page 195: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Polyurethane resins

TYPE: See table on opposite page

SUPPLIER: Dr. W. Mader AG

IDENTIFICATION: 247.2-1973

DESCRIPTION OF MATERIAL: Polyurethane two-component coating, hardened with aromatic and aliphatic diisocyanates

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position E 1 in air, dose rate 30 Gy/s Doses: 5 X 105

, l X 106, 5 X 106

, 8 X 106, 2 X 107 Gy

METHODS OF TESTING: Impact hardness, grid scarification test, and visual judgement

RESULTS: See table on opposite page

Remarks:

REFERENCES: 28

APPRECIATION: See Appendix 7

Dose (Gy)-+

111111111111

p PAINT

257

Page 196: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Q Entries and cross-references

Quartz see Ceramic

259

Page 197: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

RELAY

Resin see Thermoplastic resin see Thermosetting resin

Resistofol, trade name of Bayer see Adhesive tape

Rubber see Cable insulation see Ethylene-propylene rubber see Polychloroprene see Polyurethane rubber see Seal see Silicone rubber see Vacuum gasket

Entries and cross-references

Ryton, trade name of Phillips Petroleum, USA Polyphenylene sulfide, see Connector

Materials listed in General Tables in Appendix 5

Radox, trade name of Huber & Suhner Polyolefin, see Cable insulation, p. 21

Rayon

Rubber

Cellulose fibre, see Textile p. 28

see Cable insulation, p. 21 see Elastomer, p. 22 see G-value, p. 24 see Hose, p. 25 see Paint, p. 27

R

261

Page 198: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

R RELAY BASE MATERIAL: Various

TYPE: See table below

SUPPLIER:

IDENTIFICATION: 7-1973

Measured values*' Change after irradiation Id. Supplier C01I Test Dose Contact Standard Hysteresis Contact Hysteresis No. rating Current resistance deviation resistance

r a(r) H .'l.r1r .. 1 ,'l.H/H 0

IAI [Gyl lmnl 1%1 1%1 1%1 1%1

3 220 v.c 0 12.8 32 35.5 44 3 ..\· 103 15.2 15 32.4 27 ± 22 -9 3 I· !Oi 97 53 35.6 690 ± 420 +0.3

10 6 v.c 0.25 0 28.4 4 48.6 (4) 10 4· 103 29.2 0.5 28.6 2.8 ± 4 -41 IO I· 105 30 50.0 5.6 ± 4 +3

7 l IOV,c 0 14.5 7.9 28.6 8.2 7 4· 103 18.8 6.6 27.5 52 ± 31 -3.7 7 I· 10' 52 37 30.3 260 ± 170 +6.0 6 I IOVJc 0.25 0 14.1 29 22.5 69 6 4· !03 12.9 5 22.2 -1±1.7 -1.2 6 1 · !0

5 16.7 9.4 21.2 50 ± 43 -5.9

20 22ov1

, 0 16.4 2.5 5.2 7.0 1 4· 103 17.4 3.4 7.0 14±8 -17

14 l· 105 16.1 7.2 10.8 7±7 +0.6 20 1·10• 21.2 II 3.7 47 ± 22 -29

2 24 vd, 0 14.3 5.7 43.8 16.0 2 4· !03 17.2 4.3 42.5 24 ± 4 -3

22 24 vdc I 0 58.5 4.5 34.2 (4.5) 11 0.1 4· 103 74.6 7.7 34.2 17 ± 13 +1.4 16 0.3 I· IO' 59.2 45.7 -0.8 ± 0.6 +IO 22 I I· 10• 53.9 8.5 53.8 -8 ± 12 +57

19 220 vac 2 0 47.4 21 37.5 51 4 I 4· 103 27.2 17 29.7 160 ± 70 -6

19 2 l · 10' 59 35 33.3 30 ± 29 - II

23 60V •••) 0 16.9 .t8 93.3 11 a<

17 I· IO' 17.4 1.8 90.R ..\ ± 4.4 +2 23 I· 10° 16.8 2.0 92.1 3.8 ± 2.R -1.J

------------ -

18 ..\8 VJ, 0 13. ~ ~.'I 60.1 , ' 4· 10' .11.~ 2'1 57 1•1' ± 1.10 +J.6

18 I· 10' I~. I 12 fi0.9 ,- ±41 HU ·-----·---·-~------~----- -----------·--·----- -- -----------~- - ---------- -- ------- - ------

21 48 v () I~.: 5. I 27.3 I() J1

..\·I()' 8 12.4 '.4 li9.8 '2 ± l'I +tl.7 15 I · llJ' Iii.I 9.'i 74 . ..\ .12 ± 20 -).h

21 I· 10" I I.I I - 79.1 -'7.5 ± 3.5 + 190 9 220 \';i,,_ 0.2' 1) 12. - ~ I) 21.7 fl. I 9 ..\· 10' 1.1.1i - ' 15.'I I K ±. 12 -27

----------~----------- ------------------ --- - - ----- --- --- - ---------· -

., The har -.1gn ind1c:.t.IC'\ .i\ 1..:ra!L;n~ d\ er th(! result'.~,( ind1\·idu:ll l'~'n!cL~"). For 1t:rnJo".lc. th!.! :-an~c nf rn~:.hUrL'd "~1lu!.!~ 1-.... ;;1\Cr~ ir. pi:r....:cnt. F(1r 'h'll /c!n '!,l'-.l'. ,i \\c...·1:;htt.:d rn::an\lflhi.: raJ1at1nn dkchoftht..•:--,in~kl'(l/1 t:tLh h ~i\ L'n. 1.t: .• ti--, !h .. ' 1.l<h! "il:!:lJfi..:ant :aJ1:ll11111 ::tTL'Cl fT.l;\'ltl:"l'd 1 hc111-.... 'll'1l\\ r..

••• 1 fc'1cJ unJ~r 24 \ J,·

262

Page 199: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

R RELAY

BASE MATERIAL: Various

TYPE: See table on opposite page

SUPPLIER:

IDENTIFICATION: 7-1973

DESCRIPTION OF MATERIAL: Various types of relays for a rated load current of 10 A at 220/380 V a.c. Proposed for the Super Proton Synchrotron rough pumping station (VPTM) control units placed in intermagnet gaps, and at quadru­poles in short straight sections.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy /s Doses: I X 105

, 1 X 106 Gy; +4 X 103 Gy accelerator irradiation, CERN Intersecting Storage Rings (ISR-13-ID 1)

METHODS OF TESTING: Insulation test up to 1.5 kV. Coil resistance test. Contact resistance test at 1 A, with some exceptions. Voltage necessary for switch-on. Voltage insufficient to hold contact.

RESULTS: See table on opposite page. One relay contained an internal diode, which broke down already at 4 X 103 Gy. Generally, at 105 Gy no obvious defects were found. At 1 X 106 Gy, however, some contacts were unreliable, and obvious deterioration of plastic construction materials and insulations were observed. However, all types but one were still functional. Changes in coil resistance were generally insignificant, and contact resistance increased to some extent. Insulation test passed by all units.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

llllllllllllllllF- ~o test --+I 102 105 107 108

Dose (Gy)-+

263

Page 200: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Various

TYPE: -

SUPPLIER:

IDENTIFICATION: 38-1978

DESCRIPTION OF MATERIAL: Relay using liquid-mercury switches

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Accelerator, CERN Intersecting Storage Rings (ISR-13-ID2) Doses: 2 X 103 Gy

METHODS OF TESTING:

R RELAY

The relay was irradiated under load. Before and after irradiation, the contact resistance was measured.

RESULTS: The contact resistance was 50 mO before irradiation and increased only slightly up to about 70 mO at 2 X 103 Gy. No radiation-induced defect was found at this dose.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

no tes~ -+I 105 108

Dose (Gy)-+

265

Page 201: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

SCINTILLA TOR Polyacryl Polyvinyl toluene

Scotchcal, trade name of 3M, see Adhesive tape

SEAL (0-ring)

Entries and cross-references

Ethylene-propylene rubber (EPR) Fluorinaterd copolymer Nitrile-butadiene rubber (NBR) Polyurethane rubber (PUR) Styrene-butadiene rubber (SBR) see also Vacuum gasket see also Vacuum seal

Silica ·see Ceramic see Optical fibre

SILICON DETECTOR

Silicone oil see Insulating oil

Silicone rubber

Sleeve

see Cable insulation see Insulating sleeves see Lighting

see Insulating sleeve

Styrene-butadiene rubber (SBR) see Seal

SWITCH Glass/mica Thermoplastic resin Thermosetting resin

s

267

Page 202: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Materials listed in General Tables in Appendix 5

Saran, trade name of the Dow Chemical Co. Polyvinylidene chloride, see Textile, p. 28

Silicate oil see Oil, p. 26

Silicone oil see Oil, p. 26

Silicone resin see Paint, p. 27 see Thermosetting resin, p. 30

Silicone rubber (SIR)

Silk

Styrene

see Cable insulation, p. 21 see Elastomer, p. 22 see G-value, p. 24 see Hose, p. 25

see Textile, p. 28

see G-value, p. 23

Styrene-butadiene rubber (SBR) see Elastomer, p. 22 see G-value, p. 24

s

269

Page 203: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SCINTILLA TOR BASE MATERIAL: Polyacryl

TYPE: Plexiglas GS 1921

SUPPLIER: Roehm GmbH

IDENTIFICATION: 50.3-19 78

IO

~ ·~ • f/f(O) •

~ [%]

50 •

~ 0·~~~~-~~~~~~~~~~~~~~~~~~~~~~-~~~~-

103

270

SYMBOL

• •

104

DoselGyl

PROPERTY

transmission at 400 nm transmission at 500 nm

INITIAL VALUES

85% 93%

106

Page 204: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SCINTILLATOR

BASE MATERIAL: Polyacryl

TYPE: Plexiglas GS 1921

SUPPLIER: Roehm GmbH

IDENTIFICATION: 50.3-1978

DESCRIPTION OF MATERIAL: Acrylic scintillator, standard type of dimensions 36 X 12 X 4 mm3

; low-cost scintillator

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: a) 6°Co source Doses: a) 102

, 103, 104, 105 Gy

METHODS OF TESTING:

b) Reactor ASTRA, standard neutron irradiation facility (SNIF) b) Flux: 1016

, 10 17, 10 18

, 1019 n/m2 (E > I MeV) Dose~ 40, 400, 4 X 103

, 4 X 104 Gy

Spectral transmission between 400 and 800 nm through a sample 4 mm thick, using a Beckmann grating spectrophotometer

RESULTS: For 500 nm wavelength, the transmission decreased slowly (16% at 105 Gy). For 400 nm wavelength, however, this decrease was reached at 5 X 103 Gy, leaving only a 24% transmission at 105 Gy.

Remarks: Reference 29 contains the complete transmission spectra and further data. A fluence of 1019 n/m 2 corresponds to a dose of 2.3 X 104 Gy in polyacryl or 4 X 104 Gy in organic (CH 2)n materials

REFERENCES: 29

APPRECIATION: •••USE IN RAD/A TION AREAS ACCORDING TO APPL/CATION*** See Appendix 7

101 103

11111111111111111111111111~ 105

Dose (Gy)-+

no test I ~1 106

271

Page 205: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SCINTILLATOR BASE MATERIAL: Polyacryl

TYPE: Plexiglas GS 233

SUPPLIER: Roehm GmbH

IDENTIFICATION: 50.1-1978

f/f(O) [%1

272

0 103

SYMBOL

• •

104 10s 106

Dose[Gy]

PROPERTY INITIAL VALUES

transmission at 400 nm 90% transmission at 500 nm 91%

Page 206: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SCINTILLATOR

BASE MATERIAL: Polyacryl

TYPE: Plexiglas GS 233

SUPPLIER: Roehm GmbH

IDENTIFICATION: 50.1-1978

DESCRIPTION OF MATERIAL: Acrylic glass, UV-absorbing, of dimensions 30 X 12 X 10 mm 3

APPLICATION AT CERN: Generally used for light-guides.

IRRADIATION CONDITIONS:

Type: a) 6°Co source Doses: a) 102

, 103, 104

, 105 Gy

METHODS OF TESTING:

b) Reactor ASTRA, standard neutron irradiation facility (SNIF) b) Flux: 1016

, 10 17, 1018

, 1019 n/m2 (E > 1 MeV) Dose~ 40, 400, 4 X 103

, 4 X 104 Gy

Spectral transmission between 400 and 800 nm through a sample IO mm thick, using a Beckmann grat­ing spectrophotometer

RESULTS: For 500 nm wavelength, the transmission decreased slowly (20% at 105 Gy). For 400 nm wavelength, however, this decrease was reached at 3 X 103 Gy, leaving only a 42% transmission at 105 Gy.

Remarks: Reference 29 contains the complete transmission spectra and further data. A fluence of 1019 n/m 2 corresponds to a dose of 2.3 X 104 Gy in polyacryl or 4 X 104 Gy in organic (CH2)n materials

REFERENCES: 29

APPRECIATION: ***USE IN RADIATION AREAS ACCORDING TO APPLICATION*** See Appendix 7

llllllllllllllllllllllllllllllt- no test I ~1 101 104 106

Dose (Gy)-+

273

Page 207: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SCINTILLATOR BASE MATERIAL: Polyacryl

TYPE: Plexiglas GS 218

SUPPLIER: Roehm GmbH

IDENTIFICATION: 50.2-1978

f/f(O) [%]

50

OL__~~'------~~---"~~~J__~--'~~~---'-~~-----'~~---'-~~~·_j_~~-

IOJ

274

SYMBOL

104

Dose[Gy]

PROPERTY

transmission at 500 nm

106

INITIAL VALUES

92%

Page 208: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SCINTILLATOR

BASE MATERIAL: Polyacryl

TYPE: Plexiglas GS 218

SUPPLIER: Roehm GmbH

IDENTIFICATION: 50.2-1978

DESCRIPTION OF MATERIAL: Acrylic scintillator, standard type of dimensions 36 X 12 X 10 mm 3

, doped with 80 mg/tBBQ

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: a) 6°Co source b) Reactor ASTRA, standard neutron irradiation facility (SNIF) Doses: a) 102

, 103, 104

, 105 Gy

METHODS OF TESTING:

b) Flux: 1016, 1017

, 1018, 1019 n/m2 (E > 1 MeV)

Dose:::::: 40, 400, 4 X 103, 4 X 104 Gy

Spectral transmission between 400 and 800 nm through a sample 10 mm thick, using a Beckmann grat­ing spectrophotometer

RESULTS: For 500 nm wavelength, the decrease in transmission was 24% at 3 X 104 Gy and 33% at 105 Gy

Remarks: Reference 29 contains the complete transmission spectra and further data. A fluence of 1019 n/m2 corresponds to a dose of 2.3 X 104 Gy in polyacryl or 4 X 104 Gy in organic (CH2)n materials.

REFERENCES: 29

APPRECIATION: ***USE IN RAD/A TION AREAS ACCORDING TO APPL/CATION*** See Appendix 7

11111111111111111111111111111~ 105

Dose (Gy)-+

no test I ---.1 108

275

Page 209: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SCINTILLATOR BASE MATERIAL: Polyacryl

TYPE: Plexiglas GS 2002

SUPPLIER: Roehm GmbH

IDENTIFICATION: 50.4-1978

f/f(O) [%)

276

50

0 103 104

Dose[Gy]

SYMBOL PROPERTY

• transmission at 400 nm

• transmission at 500 nm

105 106

INITIAL VALUES

89.5% 92.5%

Page 210: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SCINTILLATOR

BASE MATERIAL: Polyacryl

TYPE: Plexiglas GS 2002

SUPPLIER: Roehm GmbH

IDENTIFICATION: 50.4-1978

DESCRIPTION OF MATERIAL: Acrylic scintillator, emitting in the near-ultraviolet spectral range. Two types: 50.41, of dimensions 36 X 12 X 10 mm 3

; 50.42, of dimensions 1000 X 200 X 3 mm 3•

APPLICATION AT CERN: Low-cost scintillator to be used in conjunction with wavelength-shifter readout techniques.

IRRADIATION CONDITIONS:

Type: a) 6°Co source Doses: a) 102

, 103, 104

, 105 Gy

METHODS OF TESTING:

b) Accelerator, CERN Intersecting Storage Rings (ISR-13-ID 1) b) 2 X 103 Gy

Spectral transmission between 360 and 600 nm using a Beckmann grating spectrophotometer (samples type 50.41). Self-absorption measurement with source placed at different distances t from the detector, counting the number of photoelectrons per minimum ionizing particle (samples type 50.42).

RESULTS: Whereas the transmission begins to decrease only at about 104 Gy ( - 18% at 400 mm), the self-absorp­tion, i.e. the quantity best characterizing the operational efficiency, has already decreased by 27 and 36% fort= 10and80cm,respectively,at 1-2 X 103 Gy

Remarks: Reference 29 contains the complete transmission spectra and further data

REFERENCES: 29

APPRECIATION: "'**USE IN RAD/A TION AREAS ACCORDING TO APPL/CATION*** See Appendix 7

11111111111111111111111111111111111111111111111111111111111~ no test I ~1 103 106 108

Dose (Gy)-+

277

Page 211: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SCINTILLATOR BASE MATERIAL: Polyvinyl toluene

TYPE: -

SUPPLIER: -

IDENTIFICATION: 220.2-19 79

150 ,----------------

IOOr----e•

f/f(O) [%]

50

-----~--·-----·--

0 '-----'----102

----'------'------------"--------'--------'

278

SYMBOL

• •

DoselGyl

PROPERTY

transmission at 410 nm transmission at 500 nm

104

INITIAL VALUES

96% 96.3%

105

Page 212: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

BASE MATERIAL: Polyvinyl toluene

TYPE: -

SUPPLIER: -

IDENTIFICATION: 220.2-1979

DESCRIPTION OF MATERIAL: Plastic scintillator of 10 mm thickness

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Accelerator a) CERN Intersecting Storage Rings (ISR-I3-ID I) b) CERN Super Proton Synchrotron (SPS-LSS5)

Doses: a) 103 Gy, b) 6 X 102, 9 X 104 Gy

METHODS OF TESTING:

s SCINTILLA TOR

Measurement of light transmission through scintillator material using a Beckmann grating spectro­photometer

RESULTS: The decrease in transmission was less than 4% up to a dose of 103 Gy. At 105 Gy, about 23% loss in transmission has been measured at 410 nm, which was the maximum in absorpti<)ll. in the visible to near ultraviolet spectral range.

Remarks:

REFERENCES: 17, 30

APPRECIATION: See Appendix 7

llllllHllllllllll~ll~ll~llllllE- no test j

Dose (Gy)-.

279

Page 213: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SEAL (0-ring) BASE MATERIAL: Ethylene-propylene rubber (EPR)

TYPE: KW 75

SUPPLIER: Angst & Pfister

IDENTIFICATION: 159.7-1973

f/f(O) [%)

50

O'--~~~~~~~~~--'-~~~~~--'-~~~~-'--~~~~~-'--~~~~--'

0

280

1.0 2.0X 106

Dose[Gy]

SYMBOL PROPERTY INITIAL VALUES

• elongation at break 202% • tensile strength 10.9 MPa 6. hardness 32 Shore D + compression set (20)

For 6., y is not normalized to f(O). The initial value given was measured under different conditions by manufacturer

3.0

Page 214: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SEAL (0-ring)

BASE MATERIAL: Ethylene-propylene rubber (EPR)

TYPE: KW 75

SUPPLIER: Angst & Pfister

IDENTIFICATION: 159.7-1973

DESCRIPTION OF MATERIAL: A ring of circular cross-section 3.53 mm and of i.d. 23.40 mm (0-ring), made from ethylene-propylene rubber (EPR)

APPLICATION AT CERN: Seals for vacuum systems in the range P > 100 Pa

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: 5 X 105, l X 106

, 3 X 106 Gy

METHODS OF TESTING: Elongation and tensile stress at break were measured with samples mounted on a silicone-lubrified fitting disk whose two halves were separated at a speed of 100 mm/min. Hardness Shore test. The compression set (modified French standard NF-T 46.011) is given as the permanent deformation in percent of the deformation under compression during irradiation (25%) as measured after a settling time of30min.

RESULTS: The elongation at break reached the 100% end-point value at 6 X 105 Gy, and the ring started to shrink at a dose of 1 X 106 Gy

Remarks:

REFERENCES: 31

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

104 10s

Dose (Gy)-+

111111111

106

281

Page 215: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SEAL (0-ring) BASE MATERIAL: Ethylene-propylene rubber (EPR)

TYPE: EPR/F 234

SUPPLIER: Gummi Maag

IDENTIFICATION: 159.5-1973

f/f(O) [%)

100

OL_~~~~_;_~~~~~~~~~---'~~~~~_L_~~~~-'-~~~~--'

282

0

SYMBOL

• • • •

1.0

PROPERTY

elongation at break tensile strength hardness compression set

For+, y is not normalized to f(O)

2.0X 106

Dose[Gyl

INITIAL VALUES

342% 11 MPa

34 Shore D

REMARKS

at5Xl05 Gy at 5 X 105 Gy

3.0

Page 216: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SEAL (0-ring)

BASE MATERIAL: Ethylene-propylene rubber (EPR)

TYPE: EPR/F 234

SUPPLIER: Gummi Maag

IDENTIFICATION: 159.5-1973

DESCRIPTION OF MATERIAL: A ring of circular cross-section 2.62 mm, and of i.d. 18. 72 mm (0-ring), made from ethylene-propylene rubber

APPLICATION AT CERN: Seals for vacuum systems in the range P > 100 Pa

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: 5 X 105

, 1 X 106, 3 X 106 Gy

METHODS OF TESTING: Elongation and tensile stress at break were measured with samples mounted on a silicone-lubrified fitting disk whose two halves were separated at a speed of 100 mm/min. Hardness Shore test. The compression set (modified French standard NF-T 46.011) is given as the permanent deformation in percent of the deformation under compression during irradiation (25%) as measured after a settling time of30min.

RESULTS: The elongation at break reached the limiting value of 100% at a dose of 3 X 106 Gy. However, the com­pression set measurement indicated a loosening of the compressed ring already at 106 Gy.

Remarks:

REFERENCES: 31

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

111111111111

101 107 108

Dose (Gy)-+

283

Page 217: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SEAL (0-ring) BASE MATERIAL: Ethylene-propylene rubber (EPR)

TYPE: EP 85 1 EN A

SUPPLIER: Walther Prazision

IDENTIFICATION: 160-1975

300.--~~~~~~~~~,-,-~~~~~~~~~-~~~~~~~-~~~~~

200

f/f(O) [%1

SYMBOL

:} ~} ~}

DIMENSIONS

Inner diameter (mm) Outer diameter (mm) Thickness (mm) Section

284

0.5

PROPERTY

elongation at break

tensile strength

hardness

TYPE a

25 37.5

4 Y-shaped

l.OX 107 1.5 Dose!Gyl

INITIAL VALUES TYPE

587% a 342% b 404% c

4.5 MPa a 8.3 MPa b 8.5 MPa c

25 Shore D a 14 Shore D c

TYPEb TYPEc

44 15 50 25 3 2

circle square

Page 218: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SEAL (0-ring)

BASE MATERIAL: Ethylene-propylene rubber (EPR)

TYPE: EP 851 ENA

SUPPLIER: Walther Prazision

IDENTIFICATION: 160-1975

DESCRIPTION OF MATERIAL: 0-rings of different cross-sections (see types a, b, c, in the table on opposite page), all made from ethylene-propylene rubber

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position 11 in water, dose rate approx. 400 Gy/s Doses: 5 X 106

, 1 X 107 Gy

METHODS OF TESTING: Elongation and tensile stress at break were measured with samples mounted on a silicone-lubrified fitting disk whose two halves were separated at a speed of 100 mm/min. Hardness Shore test.

RESULTS: Whereas the value of 100% for the elongation at break was situated between 0. 7 and 0.9 X 107 Gy for all three types of cross-sections, at 1 X 107 Gy the circular type remained the best with 83%, with the other two at half this value. The tensile stress at break remained nearly unchanged for the circular cross-section but decreased by a factor of 2.3 for type (a) and 3.5 for type (c). The hardness test also yielded different results, but was not applicable for type (b).

Remarks:

REFERENCES: 32

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

101 104 105

Dose (Gy)-+

11111~1

285

Page 219: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SEAL (0-ring) BASE MATERIAL: Fluorinated copolymer

TYPE: Viton E60C

SUPPLIER: Gummi Maag

IDENTIFICATION: 159.4-1973

200

f/f(O) [%)

oL~_J_~~I==I:====t=====±=======j 0

286

SYMBOL

• • • •

1.0 Dose[Gy]

PROPERTY

elongation at break tensile strength hardness compression set

For+, y is not normalized to f(O)

2.0X 106

INITIAL VALUES

201% 7.8 MPa

44.5 Shore D -[%]

3.0

Page 220: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SEAL (0-ring)

BASE MATERIAL: Fluorinated copolymer

TYPE: Viton E60C

SUPPLIER: Gummi Maag

IDENTIFICATION: 159.4-1973

DESCRIPTION OF MATERIAL: A ring of circular cross-section 2. 7 mm and of i.d. 18.4 mm (0-ring), made from a copolymer of viny­lidene fluoride and hexafluoropropylene (Viton)

APPLICATION AT CERN: Seals for vacuum systems not exposed to radiation.

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: 5 X 105

, 1 X 106, 3 X 106 Gy

METHODS OF TESTING: Elongation and tensile stress at break were measured with samples mounted on a silicone-lubrified fitting disk whose two halves were separated at a speed of 100 mm/min. Hardness Shore test. The compression set (modified French standard NF-T 46.011) is given as the permanent deformation in percent of the deformation under compression during irradiation (25%) as measured after a settling time of30min.

RESULTS: The elongation at break decreased very rapidly, and already reached 100% at 2.5 X 105 Gy (extra­polated). At all doses tested (above 5 X 105 Gy), the ring loosened because of shrinking during irradia­tion when compressed to 7 5%.

Remarks:

REFERENCES: 31

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

IO' 103

1111111111111 105

Dose (Gy)-+

106

287

Page 221: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SEAL (0-ring) BASE MATERIAL: Nitrile-butadiene rubber (NBR)

TYPE: PRP 138-70

SUPPLIER: Precision Rubber

IDENTIFICATION: 159.2-1973

f/f(O) 1%1

50

O·~~~~~~~~~~---'-~~~~~--'-----~~~~---'-~~~~~-'--~~~~_J

0

288

SYMBOL

• • ... •

1.0 Dose[Gyl

PROPERTY

elongation at break tensile strength hardness compression set

For+, y is not normalized to f(O)

2.0X 106

INITIAL VALUES

474% 17. l MPa

38.5 Shore D 28%

3.0

Page 222: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SEAL (0-ring)

BASE MATERIAL: Nitrile-butadiene rubber (NBR)

TYPE: PRP 138-70

SUPPLIER: Precision Rubber

IDENTIFICATION: 159.2-1973

DESCRIPTION OF MATERIAL: A ring of circular cross-section 2.6 mm and of i.d. 18. 7 mm (0-ring), made from a blend of nitrile-buta­diene rubber (NBR) with polyurethane and polychloroprene rubber, especially for use in a radiation environment.

APPLICATION AT CERN: Various vacuum seals

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: 5 X 105, 1 X 106

, 3 X 106 Gy

METHODS OF TESTING: Elongation and tensile stress at break were measured with samples mounted on a silicone-lubrified fitting disk whose two halves were separated at a speed of 100 mm/min. Hardness Shore test. The compression set (modified French standard NF-T 46.011) is given as the permanent deformation in percent of the deformation under compression during irradiation (25%) as measured after a settling time of30 min.

RESULTS: The elongation at b:-~ak reached 100% at about 2 X 106 Gy. The compression set measurements indicat­ed no loosening of the seal at 3 X 106 Gy.

Remarks:

REFERENCES: 31

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

102 104 105

Dose (Gy)-.

I 1111 108

289

Page 223: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SEAL (0-ring) BASE MATERIAL: Polyurethane rubber (PUR)

TYPE: UR 76

SUPPLIER: Angst & Pfister

IDENTIFICATION: 159.6-1973

f/f{O) [%]

50

• •

• •

• OL__~~~~--'-~~~~----'---~~~~-----'-~~~~__J'---~~~~-'--~~~~~~

0 1.0 2.0X 106 3.0 Dose[Gy]

SYMBOL PROPERTY INITIAL VALVES

• elongation at break 193%

• tensile strength 12.7MPa ... hardness 43 Shore D

• compression set

For+, y is not normalized to f(O)

290

Page 224: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SEAL (0-ring)

BASE MATERIAL: Polyurethane rubber (PUR)

TYPE: UR 76

SUPPLIER: Angst & Pfister

IDENTIFICATION: 159.6-1973

DESCRIPTION OF MATERIAL: A ring of circular cross-section 2.62 mm and of i.d. 12.3 7 mm (0-ring), made from polyurethane rubber (PUR)

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. IO Gy/s Doses: 5 X I05

, l X I06, 3 X I06 Gy

METHODS OF TESTING: Elongation and tensile stress at break were measured with samples mounted on a silicone-lubrified fitting disk whose two halves were separated at a speed of l 00 mm/min. Hardness Shore test. The compression set (modified French standard NF-T 46.011) is given as the permanent deformation in percent of the deformation under compression during irradiation (25%) as measured after a settling time of30min.

RESULTS: The elongation at break already reached IOO% value at 7 X 105 Gy. At all doses, the compression set was ~ 100%, i.e. the seal had loosened.

Remarks:

REFERENCES: 31

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

IO'

•111111 I05

Dose (Gy)-+

291

Page 225: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SEAL (0-ring) BASE MATERIAL: Styrene-butadiene rubber (SBRl

TYPE: Joinfranite S6510

SUPPLIER: Le Joint Franc;ais

IDENTIFICATION:

f/f(O) (%1

100

50

159.1-1973

---------~

0~---------~-----~----~-----0

292

SYMBOL

• • • •

1.0 DoselGyl

PROPERTY

elongation at break tensile strength hardness compression set

For+. y is not normalized to f(O)

2.0X 106

INITIAL VALUES

548% 17.8 MPa

36 Shore D 23%

3.0

Page 226: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SEAL (0-ring)

BASE MATERIAL: Styrene-butadiene rubber (SBR)

TYPE: Joinfranite S6510

SUPPLIER: Le Joint Frarn;:ais

IDENTIFICATION: 159.1-1973

DESCRIPTION OF MATERIAL: A ring of circular cross-section 2. 70 mm and of i.d. 18.40 mm (0-ring). made from styrene-butadiene rubber especially for nuclear application

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: 5 X 105

, 1 X 106, 3 X 106 Gy

METHODS OF TESTING: Elongation and tensile stress at break were measured with samples mounted on a silicone-lubrified fitting disk whose two halves were separated at a speed of 100 mm/min. Hardness Shore test. The compression set (modified French standard NF-T 46.011) is given as the permanent deformation in percent of the deformation under compression during irradiation (25%) as measured after a settling time of30min.

RESULTS: The elongation at break reached 100% at a dose of 2 X 106 Gy. The compression set measurements indi­cated no loosening at 3 X 106 Gy.

Remarks:

REFERENCES: 31

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

104 105

Dose (Gy)-+

I 111111111111

293

Page 227: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SILICON DETECTOR BASE MATERIAL: Silicon crystal

TYPE: Various, see table below

SUPPLIER:

IDENTIFICATION: 21-1976

List of particle detectors irradiated in the ASTRA reactor

Supplier Model Type Dimensions Fluence (mm' Xµm) (n/m')

ITC 29-100-456 Implanted 30.2 x 105 1 X 10" BTC 100-300-453 Surface barrier 110.4 x 305 4 x 101

FD.100.20.300 C/S/02 Keyhole s.b. 100.0 x 312 4 x 10 1•

FD.200.20.500 C/S/02 Keyhole s.b. 200.0 x 515 4 x 10 1•

TI-020-025-100/15-829A Implanted 25.0 x 101.4 1 X 10 18

TD-0 l0-030-100/15-828F Keyhole s.b. 30.0 x 90 IX 10 18

BPY-83-300/D 1464 Surface barrier 105.0 x 288 2 x 1017

030-PIN-100-TM-C-01 Diffused 30.0 x 107 1 X 10 18

100-PIN-300-TM-C-02 Diffused 100.0 x 310 4 x 10 1•

Result of defect evaluation by thermally stimulated current methods. Comparison of muon, gamma, and neutron irradiation

Material Energy level of Muons Gamma rays Neutrons

defect E = 2GeV 6°Co E> 0.1 MeV

Resistivity Type ET(eV) up to up to up to (rl ·m) 2.5 X 1017 m- 2 5.6 X l06 Gy 1018 m- 2

4 N 0.29 ± 0.02 Yes (10) No No 10 N 0.34 ± 0.02 No Yes No 46 N 0.40 ± 0.02 Yes (20) No Yes/No 46 N 0.44 ± 0.02 No Yes 00- 2) Yes 50 p 0.26 ± 0.02 Yes(3) Yes (10- 3) No

Yes and No indicate whether a certain defect was found. The values in brackets give the introduction rate of this defect: that is. the number of defects introduced per unit volume and unit irradiation tluence, in units of m- 1

294

Page 228: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SILICON DETECTOR

BASE MATERIAL: Silicon crystal

TYPE: Various, see table on opposite page

SUPPLIER:

IDENTIFICATION: 21-1976

DESCRIPTION OF MATERIAL: Silicon particle detectors (see table on opposite page) as received, and high-resistivity slices of silicon crystals, P-type and N-type, ranging from 7-90 n · m for the evaluation of defects

APPLICATION AT CERN: Particle detectors in the neutrino beam monitoring system Silicon target telescope High-resolution vertex detector (silicon microstrip detector)

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, standard neutron irradiation facility (SNIF) flux: 4.8 X 10 13 n/m2 s (E > 0.1 MeV)

Fluences: 4 X 1016, 2 X 1017

, 1 X 1018 n/m2

METHODS OF TESTING: Reverse-current measurement of the detectors; quality of 241 Am a-spectra obtained with these detectors; mechanical tests. For the raw samples, characterization of introduced defects using thermally stimulated current (TSC) techniques (Ref. 33).

RESULTS: All detectors were useless for measuring an a -particle spectrum after irradiation. Up to a fluence of "" 10 17 n/m 2, they were still useful for the detection of strong particle flux. Reverse currents increased up to about 100 mA/m2 (zero dose values: 2-20), but after one year they have recovered to 10-20 mA/m2

The TSC measurement revealed the absence of two shallow defect levels usually found in charged particle and gamma irradiation, whereas the two deeper ones were present.

Remarks: For the fluence-to-dose conversion, the factor of 4 X 10-15 Gy · m2 for (CHJn material was applied (see Section 2) for comparison purposes. The true dose in silicon is obtained by app­lying a factor of 1.2 X 10-16 Gy · m2 (Ref. 15).

REFERENCES: 33

APPRECIATION: See Appendix 7

11111111111111111111111111111

105

Dose (Gy)-+

108

295

Page 229: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SWITCH BASE MATERIAL: Glass/mica

TYPE: GV3FN; Micatherm

SUPPLIER: Burgess

IDENTIFICATION: 23-1977

f/f(O) [%)

296

50

I.OX 108

Dose[Gy]

SYMBOL PROPERTY INITIAL VALUES

e breakdown voltage case 13 kV • breakdown voltage lever 7.5 kV • dielectrical resistance core 3 X 1013 0 • dielectrical resistance lever 4 x 1012 n For• and+, y = -10 log f/f(O) has been plotted (decibels)

1.5

Page 230: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SWITCH

BASE MATERIAL: Glass/mica

TYPE: GV3FN; Micatherm

SUPPLIER: Burgess

IDENTIFICATION: 23-1977

DESCRIPTION OF MATERIAL: Microswitch: casing made from Micatherm (glass and mica); lever made from Al 20l with Teflon coating. Metallic parts were not irradiated. This switch is especially designed for nuclear applications, and of com­patible dimensions with the standard type GV3 (see Switch, made of thermosetting resin).

APPLICATION AT CERN: Used for interlock switches in the Super Proton Synchrotron splitter magnets

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position 11 in water, dose rate 400 Gy/s Doses: 5 X 107

, 1 X 108 Gy

METHODS OF TESTING: Resistance and dielectric breakdown measurements, through the Micatherm casing ( 1 mm thick)

RESULTS: The breakdown voltage decreased a little at 108 Gy but was still sufficiently high (9 .5 and 8 kV, for the casing and the lever, respectively). Also, the resistance of the casing decreased by about three decades, but still remained sufficient with 1010 n. Only the Teflon coating of the lever disappeared, indicating that there might be some increase in the force needed to operate the switch.

Remarks: See page 303 for standard version of the same type

REFERENCES: 34

APPRECIATION: See Appendix 7

101 107 108

Dose (Gy)-+

297

Page 231: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SWITCH

BASE MATERIAL: Thermoplastic resin

TYPE: -

SUPPLIER: -

IDENTIFICATION: 2-1976

DESCRIPTION OF MATERIAL: Turning switch used in vacuum equipment, rated 220 V, 10 A to 500 V, 5 A. The lever axis consists of a plastic tube, 15 0 X 60 (in mm), to cover the rather long distances from panel to equipment.

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: 2.4 X 106 Gy

METHODS OF TESTING: Operational test

RESULTS: No longer worked. Lever-handle axis damaged; plastic nut damaged.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

+-I no test ti Dose (Gy)-+

299

Page 232: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SWITCH

BASE MATERIAL: Thermoplastic resin

TYPE:

SUPPLIER:

IDENTIFICATION: 32-1979

DESCRIPTION OF MATERIAL: Limit switch, IO A. 500 V a.c .. metallic casing. Only organic materials. such as cam-rolls for pulley drive. were irradiated. The switch itself is ceramic and metal.

APPLICATION AT CERN: Limit switch for the hadron absorber in the Super Proton Synchrotron muon beam. Radiation-sensitive elements have been replaced by Vetronit (insulator) and metal parts.

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 1 X 106

, 5 X 106 Gy

METHODS OF TESTING: Qualitative mechanical test

RESULTS: Irradiated items did not break but showed increased brittleness

Remarks: As a precautionary measure, the sensitive items were replaced by more radiation-resistant ones for application at CERN

REFERENCES:

APPRECIATION: See Appendix 7

102 103 104 10~

Dose ( Gy) __.

111~1111111111111111~ bo te s t~I 106 107 108

301

Page 233: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

s SWITCH

BASE MATERIAL: Thermosetting resin

TYPE: GV3

SUPPLIER: Burgess

IDENTIFICATION: 24-1977

DESCRIPTION OF MATERIAL: Microswitch for standard applications.Case made of a thermosetting resin.

APPLICATION AT CERN: Various; CERN stores No. SCEM 06.92.32.560. 7

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. IO Gy/s Doses: 3 X 106 Gy

METHODS OF TESTING: No tests possible, broken

RESULTS: Organic parts were brittle and broken

Remarks: See page 297 for radiation-resistant version of the same type

REFERENCES:

APPRECIATION: See Appendix 7

IO' I 02 105

Dose (Gy) ~

11111111111111111

108

303

Page 234: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Tape see Adhesive tape see Insulating tape

Entries and cross-references

Teflon (PTFE), trade name of Du Pont see Heating element

Tefzel, trade name of Du Pont ETFE copolymer, see Cable tie

TERMINAL BOARD Polyester, filled

Textile Table of general relative radiation effects in Appendix 5

Thermoplastic resin Table of general relative radiation effects in Appendix 5

THERMOSETTING RESIN Table of general relative radiation effects in Appendix 5 Epoxy-phenol-novolac resin Epoxy resin

THERMOSHRINKING SHEATH

T

305

Page 235: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Materials listed in General Tables in Appendix 5

Teflon, trade name of Du Pont Polytetrafluoroethylene (PTFE) see Cable insulation, p. 21 see G-value, p. 24 see Hose, p. 25 see Thermoplastic resin, p. 29

Tefzel, trade name of Du Pont Ethylene-tetrafluoroethylene copolymer see Cable insulation, p. 21

Tetrachloromethane see G-value, p. 23

Tribromomethane see G-value, p. 23

Trichloromethane see G-value, p. 23

T

307

Page 236: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

T TERMINAL BOARD

BASE MATERIAL: Polyester, filled

TYPE: Pl

SUPPLIER: CERCEM

IDENTIFICATION: 171.3-1974

DESCRIPTION OF MATERIAL: Contact board for 1.1 kW electric motor made from mineral and glass-charged polyester

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: 1 X 106 Gy

METHODS OF TESTING: Visual only

RESULTS: Colour changed from grey before irradiation to black after 1 X 106 Gy. There were no other apparent defects.

Remarks:

REFERENCES: 19

APPRECIATION: See Appendix 7

.... 1

101 102

Dose (Gy)-+

309

Page 237: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

T THERMOSETTING RESIN BASE MA TERI AL: Epoxy-phenol-novolac resin

TYPE: EPN I 138/MY745/CY22 l/HY905

SUPPLIER: Ciba-Geigy

IDENTIFICATION: R297- I 976

s ,.M __... """" '

\ \

10 3 ~

\

\ \ !".

' "\ \

' ~

0 10 6

ABSORBED DOSE CGyl

310

D

HRTERIAL: EPN l l 38+MY 745-+ CY 22l+HY 905~XB2687

10 1 SUPPLIER: CIBA - GEIGY

REHARKS : ISR-RE:S IN

CURVE PROPERTY INITIAL VRLUE

l 0 - l S UL Tl "ATE FLEXURAL STRENGTH

10 8

0 OEFLEXIOH AT BREAK

M HOOULUS Of ELASTICITY

10- 2

128.0 MP.a

12.0 mm

38~0.0 MP a

Page 238: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

T THERMOSETTING RESIN

BASE MATERIAL: Epoxy-phenol-novolac resin

TYPE: EPN l l 38/MY745/CY22 l/HY905

SUPPLIER: Ciba-Geigy

IDENTIFICATION: R297- l 976

DESCRIPTION OF MATERIAL: Resins: EPN 1138. Araldite MY745. Araldite CY22 l (epoxy-phenol-novolac. Bisphenol A. modified): anhydride hardener HY905; accelerator XB2687 (ammonium phenolate). in the concentration of 50:50:20: 120:0.3 parts per weight. Curing: 24 hat 120 °C.

APPLICATION AT CERN: Vacuum impregnation oflntersecting Storage Rings magnet coils

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position 11 in water, dose rate 400 Gy/s Doses: 5 X 106

, 1 X 107, 2.5 X 107

, 5 X 107 Gy

METHODS OF TESTING: Standard tlexion test (ISO 1 78) according to IEC 544

RESULTS: See opposite page

Remarks: More information on thermosetting resins can be found in Part II (Ref. 2)

REFERENCES: 16

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

1111111111111

10 1 103 104 IO' 106 107

Dose (Gy)-t

108

311

Page 239: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

T THERMOSETTING RESIN BASE MATERIAL: Epoxy resin

TYPE: Araldite MY 745/HY 906

SUPPLIER: Ciba-Geigy

IDENTIFICATION: R298-l 976

N·2se S,M

" -' -, '\

\

\

'

' '\ \

\

0

ABSORBED DOSE CGyl

312

r

~

D

HATERIRL: .MY 745 -+ HY 906 -+

XB 2687

10 1 SUPPLIER: CIBA - GEIGY

REMARKS : SPS - RESIN

CURVE PROPERTY INITIAL VALUE

1 0 - l S UL Tl llATE flf:XUllAL STRENGTH

D DEfLEXION AT llllEAK

l'1 MODULUS Of ELASTICITT

10- 2

10 8

100.0 MP a

II ... mm

3780.0 MP a

Page 240: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

T THERMOSETTING RESIN

BASE MATERIAL: Epoxy resin

TYPE: Araldite MY 745/HY 906

SUPPLIER: Ciba-Geigy

IDENTIFICATION: R298- l 976

DESCRIPTION OF MATERIAL: Epoxy resin: Araldite MY 745, (Bisphenol A, modified); hardener: HY 906 (methyl nadic anhydride MNA); accelerator: XB 2687 (anmmonium phenolate) in the concentration 100:90: 1.5. Curing: 5 h at 110 °C and 16h at 125 °C.

APPLICATION AT CERN: Vacuum impregnation of Super Proton Synchrotron magnet coils

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position 11 in water, dose rate 400 Gy/s Doses: 5 X 106

, I X 107, 2.5 X 107, 5 X 107 Gy

METHODS OF TESTING: Standard flexion test (ISO I 78) according to IEC 544

RESULTS: See opposite page

Remarks: More information on thermosetting resins can be found in Part II (Ref. 2)

REFERENCES: 16

APPRECIATION: See Appendix 7

Degradation of mechanical properties:

11111111111111 101 102 103 106 108

Dose (Gy)-.

313

Page 241: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

T THERMOSHRINKING SHEATH BASE MATERIAL: Polyolefins. polyvinylidene fluoride

TYPE: See table below

SUPPLIER: Raychem

IDENTIFICATION: 151-1974

Type Property I dose in Gyl

RNF 100/l RNF 100/2 DR 25 Kynar

Base material Polyolefin Elastomer Polyolcfin Polyvinylidcnc fluoride

Wall thickness (mm) 0.3 0.3 0.5 0.2

Core diameter (mm) 4 3,4 3,4 3,4

I 105 1 7.6 6.8 6.5 5.8 External diameter (mm) I

10•1 Unchanged Unchanged Unchanged Unchanged

I 1051 White White transp. Black White transp. Colour I

10•1 White Yellow transp. Black Yellow transp.

314

Page 242: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

T THERMOSHRINKING SHEA TH

BASE MATERIAL: Polyolefins, polyvinylidene fluoride

TYPE: Sec table on opposite page

SUPPLIER: Raychem

IDENTIFICATION: 151-1974

DESCRIPTION OF MATERIAL: Tubes of thermoshrinking material (for dimensions, see table on opposite page), used as electrical insulation sleeves, made from radiation cross-linked polyolefins. and from polyvinylidene fluoride (Kynar)

APPLICATION AT CERN:

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: 1 X 105

, 1 X 106 Gy

METHODS OF TESTING: Samples of length ~ 70 to 100 mm, with the inner part shrunk on a cylindrical aluminium core of 3 or 4 mm diameter, were irradiated and afterwards tested qualitatively for elasticity and tightness of grip in the shrunken zone

RESULTS: At both doses there was no change in the external diameter of the unshrunken part nor in the tightness of the adherence of the shrunken part to the core. Disassembly is not possible by hand without tearing the sheath into pieces. The unshrunken part apparently did not lose its flexibility.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

101 103 104 105

Dose (Gy)-+

no jest __.,

106 107 108

315

Page 243: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

u Materials listed in General Tables in Appendix 5

Urea-formaldehyde see Thermosetting resin, p. 30

317

Page 244: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

VACUUM CHAMBER TUBE Epoxy/stratified glass fibres

VACUUM GASKET Synthetic rubber

VACUUM PUMP ACCESSORY Epoxy-resin/carbon

VACUUM SEAL Fluoroalkyl-polyether

VACUUM VALVE Poly amide

Valvata, trade name of Shell Mineral oil, see Insulating oil

VALVE

Entries and cross-references

Vestolene, trade name of Chemische Werke Hills AG Polyethylene, see Cable tie

V iton, trade name of Du Pont Fluorinated copolymer, see Seal

Materials listed in General Tables in Appendix 5

Vinylchloride polymers see Cable insulation, p. 21 see G-value, p. 24 see Hose, p. 25 see Paint, p. 27 see Thermoplastic resin, p. 29

Vinyl fibres see Textile, p. 28

v

319

Page 245: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

v VACUUM CHAMBER TUBE

BASE MATERIAL: Epoxy/stratified glass fibres

TYPE: S.V.E., roving type E

SUPPLIER:

IDENTIFICATION: 204-1979

DESCRIPTION OF MATERIAL: Tube of dimensions 100 mm 0 X 3.5 mm wall thickness, made from epoxy resin reinforced with 75% stratified glass fibres (circumferential direction); use intended for beam vacuum chamber sections

APPLICATION AT CERN: Vacuum pipe in fast pulsed dipole magnet (type MDFP) installed in Super Proton Synchrotron TT20

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position 11 in water, dose rate 400 Gy/s Doses: 5 X 106

, 1 X 107, 5 X 107 Gy

METHODS OF TESTING: Controlling of surface with a mechanical micrometer

RESULTS: According to the supplier, the internal surface roughness is 1 to 1.5 µm before irradiation. At 5 X 106 Gy, only a change in colour was noticed. At l X 107 Gy, bubbles about lOµm high were found at the surface, and at 5 X 107 Gy these bubbles attained a height of 200 µm and a diameter of 5 mm.

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

101 103 105

Dose (Gy)-+

lllllllllllllllll

321

Page 246: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

v VACUUM GASKET

BASE MATERIAL: Synthetic rubber

TYPE: Buna

SUPPLIER: Unknown

IDENTIFICATION: 46.2-1974

DESCRIPTION OF MATERIAL: Gaskets made from synthetic rubber (Buna) and employed in vacuum valves

APPLICATION AT CERN: Super Proton Synchrotron sector valves

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. IO Gy/s Doses: 1 X 106 Gy

METHODS OF TESTING: Operational test

RESULTS: Satisfactory operation after this dose

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

106

Dose (Gy)-+

-+I

323

Page 247: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

v VACUUM PUMP ACCESSORY

BASE MATERIAL: Epoxy resin/carbon

TYPE: -

SUPPLIER: Leybold Heraeus

IDENTIFICATION: 48-1977

DESCRIPTION OF MATERIAL: Epoxy resin coated with activated charcoal for pumping element in cryopumps

APPLICATION AT CERN: Used in cryopump for polarized hydrogen targets to be installed in the Super Proton Synchrotron vacuum system

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. IO Gy/s Doses: IX 106

, 5 X 106 Gy

METHODS OF TESTING: Remounted into equipment for operational testing

RESULTS: Operated satisfactory after these doses

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

+-bo test-+!

101 108

Dose (Gy)-+

325

Page 248: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

v VACUUM SEAL

BASE MATERIAL: Fluoroalkyl-polyether

TYPE: -

SUPPLIER:

IDENTIFICATION: 186-1976

DESCRIPTION OF MATERIAL: Vacuum feedthrough for mechanical motion transfer, consisting of an iron cylinder in an annular per­manent magnet, the gap between them being filled by magnetic fluid

APPLICATION AT CERN: Rotary feedthrough for collimator XCHV in the Super Proton Synchrotron

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. IO Gy/s Doses: 1 X 106

, 5 X 106 Gy

METHODS OF TESTING: Mechanical operational check

RESULTS: The total assembly was irradiated to I X 106 Gy, and a slight increase in viscosity of the magnetic fluid was observed. Samples of magnetic fluid were irradiated up to 5 X 106 Gy, but they were no longer usable at this dose (partially solidified).

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

105

Dose (Gy)-+

11111111111111111111

106 108

327

Page 249: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

v VACUUM VALVE

BASEMATERIAL: Polyamide

TYPE: MAC (heavy type); Nylon

SUPPLIER: VAT

IDENTIFICATION: 47-1979

DESCRIPTION OF MATERIAL: Valve with Nylonjoints

APPLICATION AT CERN: Used for fast-acting valves for the Super Proton Synchrotron vacuum system

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: l X 106 Gy

METHODS OF TESTING: Operational test

RESULTS: Nylon joints broken after this dose of l 06 Gy

Remarks: Nylon replaced by Perbunan C (chloroprene rubber) for application at CERN.

REFERENCES:

APPRECIATION: See Appendix 7

105

Dose (Gy)"""*

329

Page 250: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

v VACUUM VALVE

BASE MATERIAL: Various

TYPE: Lucifer

SUPPLIER: Sperry Vickers Lucifer S.A.

IDENTIFICATION: 46.1-1974

DESCRIPTION OF MATERIAL: Electromagnetically operated valve (vacuum equipment)

APPLICATION AT CERN: Used in sector valves in the Super Proton Synchrotron

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, switched-off reactor position 35 in air, dose rate approx. 10 Gy/s Doses: 106 Gy

METHODS OF TESTING: Operational test

RESULTS: Operated satisfactory after these doses

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

104 105

Dose (Gy)-+

106

---.1 108

331

Page 251: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

v VALVE

BASE MATERIAL: Ethylene-propylene rubber (EPR)

TYPE:

SUPPLIER: -

IDENTIFICATION: 235-1973

DESCRIPTION OF MATERIAL: Regulating piston of a Constaflo JRK automatic water regulator. type 4 f/min, made from ethylene­propylene rubber type TI 5029-1 (EPD M) of Huber & Suhner

APPLICATION AT CERN: Employed in the cooling systems for the Super Proton Synchrotron RF cavities, situated 50 cm from the beam axis

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position EI in air, dose rate 30 Gy/s Doses: 5 X 105

, 1 X 106 Gy

METHODS OF TESTING: Hardness Shore D test

RESULTS: Before irradiation, the hardness was 29 Shore D. After a dose of 5 X 105 Gy, the hardness increased by 3 7% (39.5 Shore D), and after I X I 06 Gy by 4 7% (42.5 Shore D).

Remarks:

REFERENCES:

APPRECIATION: See Appendix 7

101 102 104 105

Dose (Gy)-+

lllllllll

333

Page 252: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

Entries and cross-references

Wire see Insulated wire

WOOD

Wool

Oak wood Chipboard/mica/resin

Materials listed in General Tables in Appendix 5

see Textile, p. 28

w

335

Page 253: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

w WOOD

BASE MATERIAL: Oak wood, natural

TYPE:

SUPPLIER:

IDENTIFICATION: 242.2-1978

DESCRIPTION OF MATERIAL: Small samples of oak wood

APPLICATION AT CERN: Used in the construction of the lock-chambers for the Super Proton Synchrotron neutrino satefy access pit

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30 Gy/s Doses: 5 X 105, 1 X 106 Gy

METHODS OF TESTING: Qualitative. Flexural tests not possible because of the different orientation of the lamination.

RESULTS: No apparent damage

Remarks:

REFERENCES: 35

APPRECIATION: See Appendix 7

Dose (Gy)-+

~1 108

337

Page 254: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

w WOOD BASE MATERIAL: Wood/mica/resin

TYPE: -

SUPPLIER:

IDENTIFICATION: 242.1-1978

f/f(O) [%)

338

50

0 0

SYMBOL

• •

0.5 Dose(Gy)

PROPERTY

deflection at break flexural strength

LOX 106 1.5

INITIAL VALUES

l.Omm 4.9 MPa

Page 255: EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH · Introduction 2. Irradiation conditions 3. Presentation ofresults 4. General comparative results of radiation effects 5. Classification

w WOOD

BASE MATERIAL: Wood/mica/resin

TYPE: -

SUPPLIER:

IDENTIFICATION: 242.1-1978

DESCRIPTION OF MATERIAL: Chipboard panels made from wood and expanded mica, cut into flexural test specimens of dimensions 80 X 20 X 4 mm 2

• Fireproof material.

APPLICATION AT CERN: Used in the construction of the lock-chambers in the Super Proton Synchrotron neutrino satefy access pit (emergency exit)

IRRADIATION CONDITIONS:

Type: Reactor ASTRA, position El in air, dose rate 30Gy/s Doses: 5 X 105

, 1 X 106 Gy

METHODS OF TESTING: Standard flexural test employing the procedure in ISO 178 for rigid plastics

RESULTS: At 5 X 105 and 1 X 106 Gy, the deflection at break decreased by 35% and 42%, respectively

Remarks:

REFERENCES: 35

APPRECIATION: See Appendix 7

103 104 105

Dose (Gy)-+

111111111~ no jest ---.1 108

339