regulations for the safe transport of radioactive materials

126
SAFETY SERIES No. 6 Regulations for the Safe Transport of Radioactive Materials 1964 Revised Edition INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 1965 This publication is no longer valid Please see http://www-ns.iaea.org/standards

Upload: others

Post on 25-Jul-2022

5 views

Category:

Documents


0 download

TRANSCRIPT

Page 1: Regulations for the Safe Transport of Radioactive Materials

SAFETY SER IES

No. 6

Regulations for the Safe Transport

of Radioactive Materials1964 Revised Edition

INTERNATIONAL ATOMIC ENERGY AGENCY

VIENNA, 1965

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 2: Regulations for the Safe Transport of Radioactive Materials

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 3: Regulations for the Safe Transport of Radioactive Materials

REGULATIONS FOR THE SAFE TRANSPORT OF RADIOACTIVE MATERIALS

1964 REVISED EDITION

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 4: Regulations for the Safe Transport of Radioactive Materials

The following States ate Members o f the International A tom ic Energy Agency:

AFG H ANISTAN

ALBANIA

ALGERIA

ARGENTINA

AUSTRA LIA

A U STRIA

BELGIUM

BOLIVIA

BRAZIL

BULGARIA

BURMA

BYELORUSSIAN SO V IE T SO C IA L IS T

REPUBLIC

CAM BODIA

CAMEROON

CANADA

CEYLO N

CH ILE

CHINA COLOM BIAC O N G O , D EM O CRA TIC REPUBLIC OFC O ST A RICACUBAC ZEC H O SLO V A K SO C IA L IS T REPUBLIC

DENMARKD OM IN ICAN REPUBLICECUADOR

EL SALVADOR

ETHIOPIA

FINLAND

FRANCE

FEDERAL REPUBLIC OF GERMANY

GABON

GHANA

GREECE

GUATEM ALA

H A IT I

HOLY SEE

HONDURAS

HUNGARY

ICELAND

INDIA

INDONESIA

IRAN

IRAQISRAEL

IT A L Y

IV O RY C O A ST

JAPAN

REPUBLIC OF KOREA

K U W A IT

LEBANON

LIBERIA

LIBYA

LUXEM BOURG

M AD AGASCAR

M ALI

M EX IC O

M ONACO

M OROCCO

NETHERLANDS

NEW ZEALAND

NICARAGUA

NIGERIA

NORWAYPA K ISTA N

PARAGUAYPERUPHILIPPINESPOLANDPORTUGALROMANIA

SA U D I ARABIASENEGAL

SO U TH AFRICA

SPAIN

SUDAN

SWEDEN

SW ITZERLA N D

SYRIA

THAILAND

TU N ISIA

TU RK EY

UKRAINIAN SO V IE T S O C IA L IS T REPUBLIC

UNION OF SO V IE T SO C IA L IS T REPUBLICS

U N ITED ARAB REPUBLIC

U N ITED K IN G D O M OF G REA T BRITAIN

AND NORTHERN IRELAND

U N ITED ST A T E S OF AM ERICA

URUGUAY

VENEZUELA

V IE T -N A M

YUG OSLAVIA

T h e A g en cy 's S ta tu te was approved on 2 3 O cto b er 1 956 by th e C o n fe re n ce on th e S ta tu te o f th e

IAEA h eld a t U nited N ation s H ead q u arters, New Y o rk ; it en tered in to fo rce on 2 9 Ju ly 1 9 5 7 . T h e H eadqu arters o f th e A g en cy a re s itu a ted in V ien n a . Its p r in c ip a l o b je c t iv e is " t o a c c e le r a te and e n la rg e th e co n trib u tio n of. a to m ic en e rg y to p e a c e , h e a l th and prosp erity throughout th e w orld ".

Printed by th e IAEA in A ustria

A p ril 1965

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 5: Regulations for the Safe Transport of Radioactive Materials

SAFETY SERIES No. 6

REGULATIONS

FOR THE SAFE TRANSPORT

OF RADIOACTIVE MATERIALS

1964 REVISED EDITION

IN T E R N A T IO N A L A TO M IC E N E R G Y A G EN C Y V IEN N A , 1965

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 6: Regulations for the Safe Transport of Radioactive Materials

International Atomic Energy Agency.Regulations for the safe transport of radioĀ­

active m ateria ls . 1964 revised edition. Vienna, the Agency, 1965.104 p. (IAEA, Safety se rie s no. 6)

6 5 6 .0 7 3 .4 3 6 :5 3 9 .1 6

T H E S E R E G U L A T IO N S A R E A L SO P U B L IS H E D IN F R E N C H , R U SSIA N AND SPA N ISH

R E G U L A T IO N S F O R TH E S A F E T R A N S P O R T O F R A D IO A C T IV E M A T E R IA L S

1964 R E V IS E D E D IT IO N IA E A , V IEN N A , 1365

S T I/ P U B / 9 7

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 7: Regulations for the Safe Transport of Radioactive Materials

FOREWORDIn 1961 the In te rn a tio n a l A tom ic E n e rg y A gen cy , w ithin the

fram ew ork of its statutory functions and in accordance with recom m enĀ­dations m ade by i ts P re p a ra to r y C o m m issio n and by the E co n o m ic and S o c ia l C o u n cil o f the U nited N a tio n s1 , p u blish ed s a fe ty re g u Ā­latio n s which could be applied to the national and in ternational tra n s Ā­p o rt o f ra d io a c tiv e m a te r ia ls by a ll m e a n s o f t r a n s p o r t?

At the sam e tim e , the D ire c to r G en era l of the Agency indicated that th e s e re g u la tio n s would be re v is e d at ap p ro p ria te in te rv a ls in co n su lta tio n w ith M e m b er S ta te s and th e o rg a n iz a tio n s co n c e rn e d and invited su ggestions fo r th e ir im provem ent in the light of e x Ā­p e rie n ce and in c re a se d knowledge.

In p reparing the re v ised regulations p resen ted in th is document, the Agency has rece iv ed consid erab le support from its M em ber States and the organ ization s con cern ed , which have made exten siv e stud ies and suggestions in o rd er to a s s is t in its w ork. The Agency also conĀ­vened s e v e r a l m eetin g s of e x p e rts from its M em b er S ta te s and of re p re s e n ta tiv e s o f a num ber of in tern atio n al o rg an ization s, and has been rep resen ted in s e v e ra l m eetings convenedby those organizations.

In publishing the re v ised tran sp o rt regulations which re su lt from that co -o rd in a ted e ffo r t, the Agency a im s at proposing a lastin g fra m e w o rk o f p r in c ip le s and ru le s , co m p lem en ted by ap p ro p ria te te c h n ic a l data, a cce p ta b le fo r th e sa fe tra n s p o r t o f ra d io a c tiv e m a te r ia ls by a ir , land and w a ter. In p a r t ic u la r , the d evelopm ents which have been introd u ced con cern in g the packaging re q u irem en ts, the n u clear sa fe ty c r i t e r ia fo r the tra n sp o rt of f is s i le m a te r ia ls and the m ethods fo r te s tin g p ack ag e s should fa c i l i ta te the in te rn a tio n a l a cce p ta n ce o f p ack ag e s by the au th o rities co n cern e d .

The B o ard of G ov ernors of the Agency approved the re v ised r e Ā­gu lation s in Ju ne and S e p te m b e r 1964 . It au th orized th e D ir e c to r G e n e ra l to apply th e m , a s a p p ro p ria te , to A gency o p e ra tio n s and Agency a s s is te d op eration s and to recom m end to M em ber S ta tes and

1 RESOLUTION 7 2 4 C (X X V III)2 Regulations for th e S a fe Transport o f R ad io activ e M a te ria ls , S a fe ty Series No. 6 ,

STI/ PU B/ 40, V ien n a 1961

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 8: Regulations for the Safe Transport of Radioactive Materials

to the o rg an izatio n s co n cern ed that they be takten as a b a s is fo r r e Ā­levant national regu lation s and be applied to in tern ation al tra n sp o rt. In Septem ber 1964, the G eneral C onference of the Agency unanimously adopted a reso lu tion ? u rg ing M em b er S ta te s and the o rg a n iz a tio n s con cern ed to give e ffe c t to the D ire c to r G e n e ra l's recom m end ation .

T he re v is e d re g u la tio n s fo r th e s a fe tr a n s p o r t o f ra d io a c tiv e m a te r ia ls w ill be kept te ch n ica lly up to date in a cco rd an ce with the p ro ced u re s e t up by the A g en cy 's B o a rd o f G o v ern o rs , in the light of in creased knowledge and of the exp erien ce gained by the authorities concerned . They w ill be com plem ented from tim e to tim e by addiĀ­tio n al data. F u rth e r detailed standards fo r the packaging and testin g o f la rg e ra d io a ctiv e s o u r c e s , e s ta b lis h e d w ithin th e fra m ew o rk of the re v ise d reg u la tio n s, w ill be published in due co u rse as a re s u lt of stu d ies cu rre n tly being m ade.

3 GC(VIII)/RES/174

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 9: Regulations for the Safe Transport of Radioactive Materials

CONTENTSL ist of abbreviations .......................................................................... .... xi

PART A - GENERAL PROVISIONS .......................... ....................... 1

Scope ................................................................................................................ 1Definitions ................................... ................................................................ 1Rules for the application of the activity lim its

specified in the reg u la tio n s............................................................... 6Lim itation of exposure of persons to radiation .......................... 8Customs ......................................................................................................... 8General accident provisions ............................................................... 9

PART B - MATERIALS, INSTRUMENTS AND .ARTICLES EXEM PTED FROM PARTS C AND DOF THE REGULATIONS ............................................................... 10

PART C - REQUIREMENTS FOR PACKAGING ANDFOR DELIVERY OF PACKAGES TO TRANSPORT ___ 13

Activity lim its ............................................................................................. 13Packaging requirem ents ...................................................................... 14Other general packing requirem ents ............................................... 17Alternative packaging arrangem ents for low specific

activity m aterials ............................................................................... 19Additional requirem ents for packages containing

fiss ile m aterials ........................................................................ .. 20Adm inistrative requirem ents ............................................................ 26Additional requirem ent for delivery of a large

radioactive source to transport ................................................. 31

PART D - REGULATIONS CONCERNINGSTORAGE AND CARRIAGE .......................................................... 32

Segregation of radioactive m aterials from personsand f i l m s ................................................................................................. 32

S torag e............................................................................................................. 32

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 10: Regulations for the Safe Transport of Radioactive Materials

C arriage ....................................................................................................... 32G e n e r a l ..................................................................................... ............ 32Additional requirem ents relating to transport by:- R a i l .................................................................................................... 34- Road .................................................................................................. 35- Inland water craft ........................................................................ 35- Seagoing v esse ls ........................................................................ 35- Air .................................................................................................... 36Transport by post ........................................................................... 36

PART E - LABELS AND PLACARDS .......................................... 38

ANNEX I - GENERAL DATA ....................................................... . . . 43

ANNEX II - PACKAGING REQUIREMENTS .............................. 62

P art I - General .............................. ....................................................... 62General design features .............................................. ............. . . . 62General constructional features .............................................. 62

1P art II - Containment and radiation shielding design

principles ............................................................................................. 63

ANNEX III - FISSILE MATERIALS: METHODS OFCOMPLIANCE WITH NUCLEAR SA FETY CRITERIA . . 65

P art I - F is s ile C lass I packages ................................................... 65Schem es of ca lcu la tio n ...................................................................... 65P hysical models ................................................................................. 66Package designs complying with F is s ile C lass I crite r ia . 78

P art II - F is s ile C lass II packages ................................................ 78Package designs complying with F is s ile C lass II c rite ria . . . 78

Appendix to Annex III ............................................................................ 78

ANNEX IV - TEST PROCEDURES ................................................... 80

P art I - F o r packaging.......................... .................................................. 80G e n e r a l................................................................................................. 80Procedures for the tests referred to in C -2 . 2 . 1 . ,C-5 . 3 . 1 . 2 . (a) and (b), C - 5 . 4 . 1 . 1 . , C-5 . 4 . 1 . 3. (b),Annex II, IIā€”1.11 . and Annex III, 1 - 2 . 1 . 2 ............................. 81

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 11: Regulations for the Safe Transport of Radioactive Materials

Procedures for the tests referred to inC - 2 . 2 . 2 . and C - 2 . 2 . 3 .............. ......................................................... 84Procedures for the tests referred to in C - 2 . 3 . 1. ,C-5. 3 . 1 . 1 . (b)(i), 0 - 5 . 3 . 1 . 2 . 0 3 ) , C-5 . 4 . 1 . 2 . (b)(i),C - 5 . 4 . 1 . 3 . ( b ) , Annex II, I I - l . l l . and Annex III, 1 - 2 .1 . . 85T ests for containment and shielding in te g r ity ......................... 88

P art II - T ests for design of capsules for special formradioactive m a te r ia l .......................................................................... 89General .................................................................................................... 89Test methods ........................................................................................ 89Leakage assessm ent method ........................................................ 90

ANNEX V - SPECIFICATIONS OF PACKAGINGSFOR NON-FISSILE M A TERIALS................................................. 91

LIST OF PARTICIPANTS OF PANELS AND OTHER MEETINGS .......................................... 93

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 12: Regulations for the Safe Transport of Radioactive Materials

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 13: Regulations for the Safe Transport of Radioactive Materials

ABBREVIATIONS EMPLOYED IN THESE REGULATIONS

atm = atm osphere c = curie cm = centim etre d = dayg = gramh =hour k ca l =kilocalory kg = kilogram1 = litrem = m etreme = m illicu rie min = minute m l = m illilitre mm = m illim etre m r = m illiroentgen wt.%= weight per cent yr =; year Me =m icro cu rie luip = m icrom ho

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 14: Regulations for the Safe Transport of Radioactive Materials

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 15: Regulations for the Safe Transport of Radioactive Materials

P A R T A - G E N E R A L P R O V ISIO N S

A - l . SCOPE

A -l . 1. These regulations shall apply to the transport by air, landor water, including transport on own account, of radioĀ­active material other than that which is an integral part of the means of transport.

A - l . 2. Transport shall be deemed to include any operation inciĀ­dental to the whole course of carriage such as loading, unĀ­loading and storage.

A - l . 3. These regulations do not apply within establishm ents inwhich the radioactive material is produced, used, or stored other than in the course of transport, and in respect of which other appropriate safety regulations are in force.

A - l . 4. Compliance with these regulations, which deal only withthe hazards arising from the radioactive properties of the m aterial, shall not obviate the need for compliance with other applicable transport regulations relevant to other hazardous p ro p erties which the m a teria l p o s s e s s e s .

A-2. DEFINITIONSF o r the purpose of these regulations:

A - 2 .1 . C a r r i e rThe term "c a rrie r" includes both carriers for hire or reĀ­ward (known as common or contract ca rrie rs in some countries) and ca rrie rs on own^account (known as private ca rrie rs in some countries).

A -2 , 2. C o m p eten t a u th o r ityCompetent authority of a country shall mean any national or international authority designated or otherwise recogĀ­nized as such by that country for any purpose in connection with these regulations.

A -2 . 3. C on ta in m en t v e s s e lThe containment vessel shall mean that receptacle which is intended to retain the radioactive m aterial during transĀ­port even if receptacles within the containment vessel should break or leak.

1

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 16: Regulations for the Safe Transport of Radioactive Materials

PART A

4 . F i s s i l e m a t e r i a l sF is s i le m ateria ls shall mean plutonium-239, plutonium-241, u ra n iu m -2 3 3 , u ra n iu m -2 3 5 , o r any m a te r ia l con tain in g any of the fo reg o in g .

5. F u l l l o a dA fu ll load s h a l l m e a n any lo ad :(a) F ro m a sin gle con sig n or having the so le use of a v e Ā­

h ic le , o r of a hold o r com p artm en t of an a i r c r a f t o r of an inland w ater c ra ft, or part of a seagoing v e sse l; and ā€¢>

(b) In re sp ect of which a ll term in al and interm ediate loadĀ­ing and unloading is ca rrie d out in accordance with the in stru ction s of the consignor o r 'th e consignee.

U n le ss o th erw ise sp e c ifie d in th e s e re g u la tio n s , such a load may con sist of radioactive m ateria ls of d ifferent kinds in packages which m ay be d ifferen t and which m ay be a c Ā­companied by non-rad ioactive m a te ria l in resp ect of which m ixed loading with rad ioactive m a te r ia l is not prohibited .

6 . G r o u p s : C l a s s i f i c a t i o n o f r a d i o n u c l i d e sGroup sh a ll m ean any of the eight groups into which rad ioĀ­nuclides a re c la ss ifie d in Table II, Annex I .

7. L a r g e r a d i o a c t i v e s o u r c eL a rg e rad ioactiv e sou rce sh a ll m ean rad ioactive m ateria^ in a s in g le package having an a c tiv ity 1 g r e a te r than th e ā€™ a p p ro p ria te value s e t out as fo llo w s:(a) 5000 c for sp ecia l form radioactive m a te ria l where the

m a te r ia l is as defined in A - 2 .13. (a) o r is in a capsule as defined in A - 2 .13. (b) and the capsule is not used as the containm ent v e sse l;

. (b) In a ll other c a s e s according to the Group.

G rou pA c tiv i ty

(c )G rou p

A c tiv i ty

(c )

I 2 0 V 5 0 0 0

II 2 0 V I 5 0 0 0 0

II I 2 0 0 V II 5 0 0 0 0

IV 2 0 0 V III 5 0 0 0 0

1 Where ra d io n u c lid e s o f m o re than o n e G roup a re p resen t, see A - 3 . 4 .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 17: Regulations for the Safe Transport of Radioactive Materials

PART A 3

A - 2 . 8 . L o w s p e c i f i c a c t i v i t y m a t e r i a lLow s p e c if ic a c tiv ity m a te r ia l sh a ll m ean any of the fo lĀ­low ing:(a) U ran iu m o r th o riu m o r e s and p h y s ic a l o r c h e m ic a l

c o n c e n tr a te s of th o se o r e s :(b) U nirradiated natu ral or depleted uranium or u n irrad iĀ­

ated natural thorium ;(c) T ritium oxide in aqueous solutions provided the concenĀ­

tration does not exceed 5 .0 mc/ml;(d) M a teria l in which the activ ity is uniform ly d istributed

and in w hich the e stim ated co n cen tra tio n i p e r gram d oes not ex ce e d :

(i) 0 .0 0 0 1 m e fo r Group I rad io n u clid es ; o r(ii) 0 . 005 m e fo r Group II rad io n u clid es , o r

(iii) 0 . 3 m e fo r Groups III and IV rad ion u clid es; and(e) O b je c ts of n o n -ra d io a c tiv e m a te r ia l e x te rn a lly co n Ā­

tam in ated w ith ra d io a c tiv e m a te r ia l , provided th a t:(i) The rad io activ e m a te r ia l is in a n o n -read ily d is Ā­

p e rs ib le fo rm and the su rfa ce contam ination does not exceed :0 .0 0 0 1 m c/cm 2 fo r alpha e m itte r s of Group I o r 0 .001 m c/cm 2 fo r other radionuclides, when av e rĀ­aged over 1 m2 ; and

(ii) The o b jects a re suitably wrapped or enclosed.A - 2 . 9. M il l i r o e n t g e n p e r h o u r o r e q u iv a le n t

The m illiro e n tg e n p er hour o r equivalent sh a ll be the unit used to e x p re ss rad iatio n dose r a te s .The nu m ber o f "m illiro e n tg e n p e r hour (m r/h) o r equ iĀ­v a le n t" sh a ll be the to ta l of:(a) F o r gam m a and/or X -ra d ia tio n - the num ber of m ill i Ā­

roentgen p er hour;(b) F o r b eta rad ia tio n - the num ber of m illira d p e r hour

in a ir ;(c) F o r neutrons - the num ber of m illiro e n tg e n p e r hour

o r equivalent derived from T able III in Annex I, o r the num ber of m illire m p er hour.

In d eterm in in g d ose r a te s of rad ia tio n an ap p rop riate in Ā­stru m ent sh a ll be used and the value so m easured sh a ll be deem ed to be the actu a l dose ra te , except that neutron fluxes m ay be d eterm in e d e ith e r by c a lc u la tio n o r m e a s u re m e n t.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 18: Regulations for the Safe Transport of Radioactive Materials

4 PART A

A - 2 .1 0 .

A - 2 . 11 .

A - 2 . 12 .

A - 2 .13.

P a c k a g eP ackage shall m ean the packaging plus its radioactive conĀ­tent, as presented fo r tran sp o rt.P a c k a g in gThe packaging sh a ll m ean the assem b ly of the com ponents n e c e s s a r y to e n su re co m p lia n ce w ith the packag in g r e Ā­q u ire m en ts of th e s e re g u la tio n s . It m ay, in p a r t ic u la r , c o n s is t of one o r m o re r e c e p ta c le s , ab so rb en t m a te r ia l, sp acin g s tr u c tu r e s , ra d ia tio n sh ie ld in g and d e v ic e s fo r cooling, fo r ab sorbing m ech an ica l shocks and fo r th erm al insu lation .R a d io a c t iv e m a t e r i a lR ad ioactive m a te ria l sh a ll m ean any m a te ria l of which the sp e c ific activ ity is g re a te r than 0 .0 0 2 /uc/g.S p e c ia l fo r m r a d io a c t iv e m a t e r ia lR ad io activ e m a te r ia l is deem ed to be in sp e c ia l fo rm if it m eets the follow ing re q u irem en ts:(a) The rad ioactive m a te ria l is in m assiv e solid form which:

(i) E ith er has no o v e r -a ll dim ension le s s than 0. 5 mm, or has at le a s t one dim ension of not le s s than 5 mm; and

(ii) Does not m elt, sublim e or ignite at tem p eratu res up to 538Ā°C ; and

(iii) W ill not b reak o r sh a tter if sub jected to the p e rĀ­cu ss io n te s t sp e c ifie d in Annex IV , I Iā€”2. 2. and

(iv) D oes not d isso lv e o r convert into d isp e rs ib le r e Ā­action products by m ore than 50/ng/g of m a te ria l during one w eek's im m ersion in w ater at pH6-pH8 and at 20Ā° C, w ith a m axim um con d u ctiv ity of 10 ixj/j / cm ; and

(v) D oes not co n v ert into d is p e rs ib le re a c tio n p ro Ā­d ucts by m o re than 50 Mg/g o f m a te r ia l during one w e e k 's e x p o su re to a i r a t 3 0 Ā°C ; o r

(b) The rad ioactive m a te ria l is contained in a capsule which has no o v e r -a ll d im ension le s s than 0 . 5 mm or has at le a s t one d im ension of not le s s than 5 m m . The capĀ­su le i s co n s tru cte d of m a te r ia ls w hich m e e t the r e Ā­q u ire m en ts of A - 2 . 13 . (a), (ii) , ( iii) , (iv) and (v) e x Ā­cep t that the te m p e ra tu re in (ii) s h a ll be 8 0 0 Ā°C , and the capsule design is dem onstrated to sa tisfy the te s ts in Annex IV , P a r t I I .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 19: Regulations for the Safe Transport of Radioactive Materials

PART A 5

(a) The tra n sp o rt index fo r a package is :(i) The nu m ber e x p re ss in g the m axim um rad ia tio n

dose ra te at 1 m fro m the ce n tre of the package; o r

(ii) When any o v e r -a ll external dim ension of the packĀ­age exceed s 2 m, the num ber exp ressin g the la rg e r of the follow ing:

the m axim um radiation dose ra te at the su rface at the end of the long a x is of the package; and, w here ap p rop riate ,the m axim um rad iatio n dose ra te at a d istan ce of 1 m p erp en d icu lar to the long a x is of the p ackage; o r

(iii) F o r a F i s s i le C la ss II package, the la rg e r of the follow ing nu m bers:the n u m b er e x p r e s s in g the m axim u m ra d ia tio n d ose r a te under (i) o r (ii) ab ove; and the num ber obtained by dividing 50 by the allow Ā­ab le n u m b er2 of such p ack ag es;

(b) T h e tr a n s p o r t index fo r a fu ll load 3 o f low s p e c if ic activ ity m a te r ia l is the num ber exp ress in g the m ax iĀ­mum dose ra te at any point 1 m fro m the load, m u ltiĀ­p lied by the valu e in T ab le VI of Annex I ap p ro p ria te to the weight o r the c r o s s -s e c t io n a l a r e a of the load . F o r uranium o r thorium o res and physical o r chem ical co n c e n tra te s of th o se o r e s , in the a b se n ce o f a ctu a l m easurem ent o r calcu lation , the m axim um dose ra te s at any point 1 m fro m the load m ay be taken a s :

40 m r/h o r equivalent fo r uranium o re s and physical' co n cen tra tes ;10 m r/h o r equivalent fo r thorium o re s and physical co n cen tra tes ;2 mr/h or equivalent fo r uranium and thorium chem iĀ­ca l con cen trates;

(c) T he n u m ber e x p re s s in g the tra n sp o rt index s h a ll be rounded up to the f i r s t d e c im a l p la c e .

A -2 . 14. T ra n sp o r t in d e x

2 S e e C - 5. 4 . 1. 3 .

3 S e e C - 4 . 2 .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 20: Regulations for the Safe Transport of Radioactive Materials

6 PART A

A -2 . 15 . V e h ic l eV eh ic le sh a ll m ean road v e h ic le (including an articu la ted v e h ic le , i . e . a t r a c to r and s e m i- t r a i le r com bination) o r ra ilr o a d c a r o r ra ilw ay w agon. A t r a i l e r sh a ll be co n Ā­s id e re d a s a s e p a ra te v e h ic le .

A - 3 . R U L E S F O R T H E A P P L IC A T IO N O F T H E A C T I V I T Y 'L IM IT S S P E C IF IE D IN T H E R E G U L A T IO N S

A - 3 .1. C la s s i f i c a t io n o f in d iv id u a l r a d io n u c l id e s in to g r o u p s f o rt r a n s p o r t p u r p o s e s

A - 3 .1 .1 . Any radionuclide listed in Table II of Annex I shall be c la s Ā­sified in accord ance with that tab le .

A -3 . 1. 2. Any rad ionuclide not lis te d in T ab le II of Annex I, but the id en tity of w hich is known, sh a ll be c la s s if ie d a cco rd in g to i t s a to m ic n u m b e r and p h y s ic a l h a l f - l i f e a s fo llo w s :

P h y s ic a l h a l f - l i f e

A to m ic N o .

0 - 1 0 0 0 d1 0 0 0 d

to 106 yr

O v er l t f

yr

1 - 8 1 G rou p II I G rou p II G rou p II I

8 2 and a b o v e G rou p I G rou p I G rou p HI

A - 3 .1. 3 . Any radionuclide the identity of which is not known sh all be c la ss ifie d as Group I.

A -3 . 2 . C la s s i f ic a t io n o f c e r ta in m ix tu r e s o f r a d io n u c lid e s and the a c t iv ity o f su ch m ix tu r e s

A -3 . 2 .1 . M ixed f is s io n produ cts, a s produced during the fis s io n of f is s i le m a te r ia ls , sh a ll be c la ss if ie d as Group II ; the a c Ā­t iv ity o f su ch a m ix tu re s h a ll be the to ta l a c tiv ity o f a l l the ra d io n u c lid e s p re s e n t .

A - 3 . 2 . 2 . M ix tu re s c o n s is t in g o f a s in g le ra d io a c tiv e d eca y ch a in w here the radionuclides a re in the naturally occu rring proĀ­portions shall be considered as consistin g of a single radionuclide.The group and a c tiv ity sh a ll be that of the f i r s t m e m b er p re s e n t o f the ch a in , e x ce p t i f a rad io n u clid e " X " h as a h a lf - l ife lo n g er than that of that f i r s t m em b er and an a c Ā­tiv ity g re a te r than that of any o th er m em b er including the

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 21: Regulations for the Safe Transport of Radioactive Materials

PART A 7

f i r s t at any tim e during tra n sp o rt; in that c a s e , the group of the m ix tu re sh a ll be the group of that nu clide " X " and the activ ity of the m ix tu re sh a ll be the m axim um activ ity of that nuclide " X " during tra n sp o rt.M ix tu re s c o n s is t in g of a s in g le ra d io a c tiv e d ecay ch a in where one o r m ore radionuclides are in proportions g rea ter than th o se n a tu ra lly o ccu rr in g , due to a r t i f ic ia l p h y sica l o r ch e m ica l e n rich m en t:T he m e m b er o r m e m b e rs of the ch ain w hich a r e in p ro Ā­p o rtio n s g r e a te r than th o se n a tu ra lly o c c u rr in g sh a ll be tre a te d a s s e p a ra te ra d io n u c lid e s ; the r e s t of the ch a in s h a ll be tre a te d a s A - 3 . 2 .2 . ab ov e .A c t iv i t y o f u ra n iu m o r n a tu r a l t h o r iu m .The activ ity of uranium o r natural thorium shall be as c a lĀ­cu lated by u sin g the a c t iv i ty -m a s s re la tio n sh ip g iven in T a b le I of A nnex I .R u le s f o r d e t e r m in in g th e p e r m i s s i b l e a c t iv i t i e s o f in d i Ā­v id u a l r a d i o n u c l id e s in th e c a s e w h e r e s e v e r a l d i f f e r e n t r a d io n u c l id e s a r e c o n ta in e d t o g e t h e r in a s in g le p a c k a g e . I f the id en tity and the re s p e c t iv e a c tiv ity of each ra d io Ā­nuclide a re known, the p e rm iss ib le activ ity of each rad ioĀ­nuclide sh a ll be such that the sum F j + F 2 + . . . + Fs is not g re a te r than unity, w herep _ to ta l activ ity of the radionuclides of Group I_________

1 applicable activ ity lim it per package for radionuclidesof Group I,

F _ to ta l activ ity of the radionuclides of Group II________2 applicable activ ity lim it per package for radionuclides

of Group II,p ā€™ _ to ta l activ ity of the radionuclides of Group VIII_____

8 applicable activ ity lim it p er package for radionuclidesof Group VIII.

N ote: M ix tu re s under A -3 . 2 . 2. a re to be co n sid ere d as a s in g le rad io n u clid e .

F o r the purpose of applying the above form u la in the ca se w here the id en tities of a ll rad ionuclides a re known but the re s p e c t iv e a c t iv it ie s of a l l of th em o r so m e of them a re not known, a ll the rad ionu clid es the re sp e c tiv e a c tiv it ie s of w hich a r e not known s h a ll be d eem ed to b elon g to the m o re r e s tr ic t iv e groups am ong them ; (th e ir to ta l activ ity m u st n e c e s s a r i ly be known, e ith e r d ir e c t ly , o r by s u b -

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 22: Regulations for the Safe Transport of Radioactive Materials

PART A

tr a c t in g the to ta l a c tiv ity of th o se ra d io n u clid e s the r e Ā­sp ectiv e a c t iv it ie s of w hich a re known fro m the to ta l a c Ā­tiv ity of the con ten ts of the p ack ag e).I f the id en tity of a l l o r som e rad io n u clid es is not known, th o se rad io n u clid es sh a ll be deem ed to belong to Group I a s ind icated in A -3 . 1 . 3 . above.

A- 4 . LIMITATION OF EXPO SU RE OF PERSONS TO RADIATION

A -4 . 1. No p erso n s sh a ll be exposed to re c e iv e rad iatio n d oses ine x c e s s of the m axim um p e rm iss ib le lev e ls fo r the various c a te g o r ie s of p e rso n s sp e cifie d in the b a s ic sa fe ty s ta n Ā­d a rd s4 of the In te rn a tio n a l A tom ic E n e rg y A gency.

A - 4 . 2. T ra n s p o rt and s to ra g e p e rso n n e l sh a ll not be exposed tore ce iv e rad iation d oses in e x ce ss of those dpses perm itted fo r w o rk ers not d ire c tly engaged in rad iatio n work un less arrangem ents have been made to comply with the competent a u th o r ity 's p ro v is io n s w ith r e s p e c t to w o rk e rs d ir e c t ly engaged in ra d ia tio n w ork .

A -4 . 3 . P e r io d ic a s s e s s m e n ts sh a ll be c a r r ie d out to en su re thatthe m axim um lev e ls of exposure for the various ca teg o ries of p ersons a re not being exceeded. Radiation surveys shall be undertaken when th e re is re a so n to suppose that th e se le v e ls a re being approached.

A -4 . 4 . W ork ers sh a ll re ce iv e such in stru ctio n s as a re n e ce ssa rycon cern in g the hazard s involved and the p recau tio n s to be ob serv ed .

A -5 . CUSTOMS

C ustom s operation involving exam ination of the contents of a package in which rad ioactive m a te ria ls a re being shipped sh a ll be c a r r ie d out in a p lace w h ere adequate m ean s of radiation exposure con tro l a re provided and/or in the p re Ā­sence of qualified p erson s. Any package opened on custom s

4 B a s ic S a fe ty S tan d ard s for R a d ia tio n p ro te c tio n , S T I/ P U B / 26 , S a fe ty S e r ie s N o. 9 .

T h e s e standards a r e b a se d , to th e e x te n t p o ssib le , on th e re co m m e n d a tio n s o f th e In te rn a tio n a l C o m m iss io n on R a d io lo g ic a l P ro te c t io n .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 23: Regulations for the Safe Transport of Radioactive Materials

PART A 9

instru ction s shall, before being forwarded to the consignee at its final destination, be resto red to its orig in al condition.

GEN ERA L ACCIDENT PROVISIONS

In the event of a package of rad ioactive m a te ria ls suffering b rea k a g e o r leak ag e , o r becom ing involved in a c ra s h , w reck o r f ire , the affected p lace sh a ll be iso la ted to p re Ā­vent a ll contact of p erson s with any loose rad io activ e m aĀ­t e r ia l and, when p ra c t ic a b le , posting o r fencing sh a ll be provided. No p erso n s sh a ll be allow ed to e n te r o r to r e Ā­m ain w ithin the iso la ted p lace until qualified p erso n s a re av ailab le to check rad iatio n h azard s and su p erv ise the handling o r sa lv a g e . The con sig n or and ap p rop riate a u th o rities sh a ll be notified im m ed ia te ly .Notwithstanding anything in A - 6 . 1. above the p re se n ce of rad io activ e m a te r ia l sh a ll not be taken as a b a r to re scu e op eration s o r fighting of f ire by qualified p e rso n s .All persons who may have becom e contaminated with radioĀ­a c tiv e m a te r ia ls s h a ll be su b je c t to a p p ro p ria te co n tro l and exam in atio n m e a s u re s .Any conveyance, building, place, equipment, or part th e re Ā­of which has becom e contam inated as a re su lt of an a c c i Ā­dent in the co u rse of tra n sp o rt of ra d io a ctiv e m a te r ia ls sh a ll be d econtam inated by qualified p e rso n s a s soon as p o s s ib le and p r io r to i t s b e in g put b a ck in to s e r v i c e .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 24: Regulations for the Safe Transport of Radioactive Materials

P A R T B - M A T E R IA L S , IN S T R U M E N T S AND A R T IC L E S E X E M P T E D F R O M P A R T S C AND D

O F T H E R E G U L A T IO N S

B - l . The m a te r ia ls , in stru m en ts, a r t ic le s and empty packagessp ecified under B - l . 1 . , B - l . 2 . , B - l . 3 . and B - l . 4 . below sh a ll be exem pted fro m a l l p ro v isio n s of P a r t C, excep t the notes under the tit le , and of P a r t D, which a re not ex Ā­p re s s ly retained in th is P a rt provided that:(a) The d ose ra te at any point on the e x te rn a l s u r fa c e of

the package does not exceed 0 . 5 m r/h o r equ ivalent;(b) The non-fixed radioactive contam ination on any external

s u rfa ce of the package does not exceed the le v e ls laid down in T ab le IV of Annex I ; and

(c) E x ce p t fo r a r t ic le s d escrib e d in B - l . 3 . , the package d oes not co n ta in m o re than 15 g of u ran iu m -233 , o r 15 g of uranium -235, o r 15 g of plutonium-239, or 15 g of plutonium -241, o r 15 g of any com bination of th ese ra d io n u clid e s .

B ā€”l . l . M a t e r i a l sR a d io a c tiv e m a t e r i a l s 1 not e x c e e d in g :(a) 0 .0 1 m e of rad ion u clid es of Group I p e r p ackag e; o r(b) 0 .1 m e of rad io n u clid es of Group II p e r p ackag e; o r(c) 1 m e of rad ion u clid es of Group III, IV , V o r VI o r of

m a te ria l in sp ecia l form as defined in A - 2 .13. (a), per package; or

(d) 1000 m e o f ra d io n u clid e s o f G roups V II o r V III p e r package o r , fo r tr it iu m oxide in aqueous so lution , a co n cen tra tio n of 0 . 5 m e/m l,

provided that these m a te ria ls a re packed in such a m anner th at, under n o rm al conditions of tra n sp o rt, th e re can be no leak ag e of ra d io a ctiv e m a te r ia l.The containm ent v e s s e l sh a ll b e a r the m arking "R ad io acĀ­t iv e " in su ch a m an n er th at it w ill be v is ib le b e fo re the co n ta in m en t v e s s e l can be opened.

B - 1 . 2 . I n s t r u m e n t s a nd a r t i c l e sInstru m ents such as c lo ck s , e le c tro n ic tubes o r apparatuses, o r o th er m an u factu red goods o r d e v ic e s , having ra d io Ā­a c tiv e m a te r ia ls in a n o n -re a d ily d is p e r s ib le fo rm a s a

1 Where radionuclides of more than one Group are present, seeA -3 .4 .

10

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 25: Regulations for the Safe Transport of Radioactive Materials

PART B 11

component part provided that these instrum ents, apparatuses o r d e v ice s a r e s e c u re ly packed in s tro n g p a ck a g e s , and the conditions in B - l . 2. 1 . , B - l . 2 . 2 . , a n d B - 1 .2 .3 . below a re fu lfilled .

B - l . 2 .1 . The a c tiv ity 1 of an in stru m en t, p iece of apparatus o r d eĀ­v ice sh a ll not exceed :(a) 0 .1 m e of rad ion u clid es of Group I ; o r(b) 1 m e of rad ion u clid es of Group II; o r(c) 10 m e of rad ionu clid es of Group III; o r(d) 50 m e of rad ionu clid es of Group IV ; o r m a te r ia l in

s p e c ia l fo rm as defined in A - 2 . 13 . (a); or(e) 1 c of rad ion u clid es of Group V o r V I; o r( f ) 200 c of rad ion u clid es of Group V II; or(g) 10 c of rad ion u clid es of Group V III.

B - l . 2 . 2 . T h e ra d ia tio n d ose ra te at 10 cm fro m any unpacked in Ā­s tru m en t, ap p aratu s o r d ev ice sh a ll not exceed 10 m r/h o r equ iv alen t.

B - l . 2. 3 . The to ta l a c tiv ity 1 p e r package sh a ll not exce e d :(a) 1 m e of rad io n u clid es of Group I ; o r(b) 50 m e of rad io n u clid es of Group II ; o r(c) 3 c of rad io n u clid es of Group III o r IV ; o r(d) 20 c fo r m a te ria l in sp ecia l form as defined in A - 2 .13. (a);

or(e) 1 c of radionuclides of Group V or VI; or(f) 200 c of radionuclides of Group V II; or(g) 1000 c of radionuclides of Group V III.

B - l . 3. M anufactured a r t ic le s , o ther than fuel e lem en ts, in which the so le rad io activ e m a te ria l is natu ral o r depleted u ran iĀ­um, provided that the outer su rface of the uranium is enĀ­c lo sed in an in a c tiv e m e ta llic sh eath (su ch a r t ic le s m ay be packagings fo r the tra n sp o rt of rad io activ e m a te r ia ls ) . The to ta l a c tiv ity p e r a r t ic le sh a ll not exceed 3 c .

B - l . 4 . E m p ty p a c k a g e sA package having contained ra d io a c tiv e m a te r ia ls , p ro Ā­vided that i t has b een cleaned in te rn a lly , and is s e c u re ly c lo sed and in good condition.On the re s p o n s ib ility of the co n s ig n o r the ou tsid e of the p ackage sh a ll be m ark ed : "E m p ty packaging having co n Ā­tained ra d io a ctiv e m a te r ia ls " . The m ark in g req u ired in

1 Where radionuclides of more than one Group are present, see A -3 .4.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 26: Regulations for the Safe Transport of Radioactive Materials

12 PART B

C - 3 .5 .4 . and C - 3 .5 .6 . and the labels conform ing to P a r tE , F ig s . 2, 3, or 4 shall not be visible'.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 27: Regulations for the Safe Transport of Radioactive Materials

P A R T C - REQ U IREM EN T S FO R PACKAGING AND FO R D E L IV E R Y O F PACKAG ES TO TRAN SPO RT

N O T E S: 1. T h e t r a n s p o r t o f e x p lo s iv e r a d io a c t iv e m a t e r i a l s s h a l ln o t b e p e r m i t t e d e x c e p t u n d e r s p e c i a l a r r a n g e m e n t s a p p r o v e d b y th e c o m p e t e n t a u t h o r i t i e s c o n c e r n e d .

2 . F o r p y r o p h o r i c m a t e r i a l s s e e C ~6. 2 . 1 ,

C - l . A C T IV IT Y L IM IT S

C - l . 1. Packaging conform ing to the requ irem ents of s e c tio n C -2 . 2.fo r Type A packaging d esign and which does not m eet the additional re q u irem en ts of C~2. 3 . sh a ll not contain m ore than the a c tiv ity ! indicated below :(a) F o r s p e c ia l fo rm ra d io a c tiv e m a te r ia ls w h ere the

m a te r ia l is a s defined in A - 2 . 13. (a) o r is in a capsule a s defined in A -2 . 13 . (b) and the cap su le is not used a s the containm ent v e s s e l : 20 c

(b) In a l l o th er c a s e s a cco rd in g to the Group.

GroupMaximumac tivity(me)

GroupMaximu m

act iv ity(c)

GroupMaximum

ac tivity(c)

I 1 III 3 VI 1000

II 50 IV 20 VII 1000

V 20 VIII 1000

C - 1 .2 . P ack ag in g co n fo rm in g to the re q u ire m e n ts of C - 2 .3 . f o r Type B packaging d esign and which does not m eet the adĀ­d itio n a l re q u ire m e n ts of C - 2 .4 . , s h a l l not co n ta in m o re th an th e a c t iv i ty 1 in d ica ted below :(a) F o r sp e cia l form rad ioactive m a te ria ls w here the m aĀ­

t e r ia l is a s defined in A - 2 . 13 . (a) o r is in a cap su le as defined in A - 2 . 13 . (b) and the cap su le is not used as the co n tain m en t v e s s e l : 5000 c

(b) In a l l o th er c a s e s a cco rd in g to the Group.

1 Where radionuclides of more than one Group are present, see A -3 .4.

1 3

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 28: Regulations for the Safe Transport of Radioactive Materials

1 4 PART C

GroupMaximum

act ivity(c)

GroupMaxim um

ac tivity(c)

20 v V 5 000

11 20 VI 50 000

111 200 VII 50 000

IV 200 VIII 50 000

C - 2 . PACKAGIN G R E Q U IR E M E N T S

C - 2 . 1 . G e n e r a l p a c k a g in g r e q u i r e m e n t sC - 2 . 1 .1 . A ll packaging sh a ll m eet the g e n e ra l packaging r e q u ir e Ā­

m ents in Annex II, P a r t I .C -2 . 1 .2 . W ith re s p e c t to the m aintenance of containm ent and ra d iĀ­

a tio n sh ie ld in g , p ackaging sh a ll be e ith e r Type A o r Typ e B 5 .

C - 2 . 2 . A d d it io n a l r e q u i r e m e n t s f o r T y p e A p a c k a g in gC -2 . 2 .1 . In addition to the requ irem en ts in Annex II, P a r t I, Type A

packaging sh a ll be designed in a cco rd a n ce with the p rin Ā­c ip le s given in Annex II, P a r t II, and sh all be adequate to p rev en t the lo s s o r d is p e r s a l of the ra d io a ctiv e contents and to re ta in the e ffic ie n cy of its rad iatio n sh ield ing p roĀ­p e r t ie s i f the package w ere su b je c te d to the te s t s s p e c iĀ­fied in Annex IV , 1 -2 .

C -2 . 2. 2 . Type A packaging designed fo r liquids sh a ll in addition bead equate to p re v e n t lo s s o r d is p e r s a l of the ra d io a c tiv e contents if the package w ere sub jected to the te s t specified in Annex IV , 1 -3 , u n less su ffic ie n t ab so rben t m a te r ia l is provided within the containm ent v e s s e l to absorb tw ice the volum e of the liquid contents and:(a) The ab so rben t m a te r ia l is within the rad iation sh ield ;

o r(b) The absorbent m a te ria l is outside the radiation shield,

provided that it can be shown that if the liquid contents w ere taken up by the ab sorbent m a te r ia l the resu ltan t d ose ra te at the s u rfa ce of the package would not e x Ā­ceed 1000 m r/h o r equ iv alent.

C -2 . 2. 3. Type A packaging designed for gases in quantities in excess of 20 c sh a ll in addition be adequate to prevent lo ss or d isĀ­

See however C-4.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 29: Regulations for the Safe Transport of Radioactive Materials

PART C 1 5

p e rsa l of the rad ioactive contents if the containm ent v e sse l of that packaging w ere se p a ra te ly su b jected to the te s t sp ecified in Annex IV , 1 -3 .

C - 2 . 2 . 4 . Type A p ackag in g d esign ed fo r g a m m a -e m itt in g ra d io Ā­a c tiv e m a te r ia l in q u an tities in e x c e s s of 3 c and in c o r Ā­porating a rad iation shield of m a te ria l with a m elting point of le s s than 815Ā°C sh a ll have a s te e l containm ent v e s s e l . T h is containm ent v e s s e l sh a ll have no e x te rn a l dim ension le s s than 5 cm and the th ick n e ss of the s te e l sh a ll not be le s s than 2 m m .

C - 2 . 3 . A d d it io n a l r e q u i r e m e n t s f o r T y p e B p a c k a g i n g C - 2 . 3 . 1 . Type B p ackaging sh a ll m e e t the re q u ire m e n ts under

C -2 . 2 .1 . and in addition, if it w ere su b jected to the te s ts sp ecified in Annex IV , 1 - 4 . , m ust be adequate:(a) To prevent the lo ss o r d isp e rsa l of the rad ioactive conĀ­

ten ts ; and(b) To re ta in sufficien t of its radiation shielding prop erties

to ensure that the rad iation lev el at 1 m from the su rĀ­fa ce of the packaging does not exceed 1000 m r/h had the packaging contained su ffic ien t irid iu m -192 to p roĀ­duce 10 m r/h at 1 m from the su rface of the packaging b efo re being sub jected to the te s ts .I f a Type B p ackaging is to be used fo r a p a r t ic u la r ra d io n u clid e , th at rad io n u clid e m ay be used a s the r e fe r e n c e s o u rc e in p la ce o f ir id iu m -1 9 2 .

C - 2 . 3 . 2 . Type B packaging sh a ll in addition be adequate to en su re that the containm ent v e s s e l w ill re m a in lea k p ro o f at a depth of 15 m in w a ter .

C - 2 . 4 . A d d it io n a l r e q u i r e m e n t s f o r p a c k a g e s c o n ta in in g l a r g e r a d i o a c t i v e s o u r c e s

C -2 . 4 . 1 . The packaging sh a ll m eet the re q u irem en ts under C - 2 . 3. C -2 . 4 . 2 . The package sh a ll be so designed and con stru cted :

(a) That' the heat generated within the package b ecau se of the rad ioactive m a te r ia ls p resen t w ill not, at any tim e during tra n sp o rt, a ffe c t the e ffic ie n cy of the package under the cond itions encou ntered in tra n sp o rt. P a r t ic u la r attention sh a ll be paid to the e ffe c ts of heat which m ay:

(i) A lte r the g e o m e trica l fo rm or the p h y sica l state of the so u rce o r , i f the m a te r ia l is en clo sed in a can o r re c e p ta c le (for exam p le , clad fu el e le -

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 30: Regulations for the Safe Transport of Radioactive Materials

1 6 PART C

m ents) cause the can, re ce p ta c le or the m a te ria l to m elt;

(ii) L e s s e n the e ffic ien cy of the package by the m e ltĀ­ing of the ra d ia tio n sh ield in g m a te r ia l o r the crack ing of the container due to therm al s tre s s e s ;

(iii) A cce lera te co rro sio n in com bination with m oistu re.(b) That the tem p eratu re of the a c c e ss ib le su rfa ces of the

package sh a ll not exceed 50Ā°C in the shade when fully load ed assu m in g s t i l l , am b ie n t a i r a t 3 8 Ā°C . O th er am bient a i r cond itions w hich co rresp o n d to en v iron Ā­m en ta l cond itions of tra n sp o rt m ay be assu m ed upon ap p roval by the com p etent au th o rity . I f the package is tra n sp o rte d a s a fu ll load the l im it of 5 0 Ā° C above s h a ll be ra is e d to 8 2 Ā° C .

C - 2 .4 .3 . I f a coolant o r cooling sy stem is provided, it sh a ll sa tisfythe follow ing conditions:(a) The p rim a ry gas o r liquid coolant sh all not be circu la ted

outside the rad iation shield of the co n ta in er; 6(b) If a cooling sy stem is provided, fa ilu re of that system

sh a ll not re s u lt in the uncontro lled r e le a s e of ra d io Ā­a ctiv e m a te r ia ls ;

(c ) W hen a liq u id co o la n t i s u sed , and u n le s s i t ca n be shown that the fre e z in g of the coo lan t w ill not ca u se dam age to the container o r contents, precau tions shall be taken to prevent fre e z in g of that coolant during tra n sp o rt, o r su itab le u llage o r "o u tag e" o r o th er m eans shall be provided to prevent freezing from cau sĀ­ing damage to the container or its contents 6.

(d) I f a liquid coolant is used and te m p e ra tu re s inside the co n ta in er m ay re a ch the boiling point of the coolant at any tim e during tra n sp o rt, the co n ta in er sh a ll be d eĀ­signed and con stru cted to withstand the in te rn a l p r e s Ā­su re developed without lo s s of coo lant, co n ta in er e f Ā­f ic ie n c y o r r e le a s e o f ra d io a c tiv e m a te r ia ls . I f the co n ta in e r is not designed to m e e t the above r e q u ir e Ā­m e n ts , the s y s te m s h a ll be d esign ed to r e s t r i c t the liquid te m p e ra tu re in sid e the co n ta in er and in the v iĀ­c in ity of the rad ioactiv e m a te r ia ls to at le a s t 10Ā°C be~

6 Paragraphs C -2 .4 .3 .(a ) , C -2 .4 .3 .(c ) , C -2 .4 .3 .(d ) and C -2 .4 .4 . are provisionallyretained pending the results of further study by a group of experts in 1965/66.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 31: Regulations for the Safe Transport of Radioactive Materials

PART C 17

low the b o ilin g point of the liquid , due acco u n t being taken of the e x tern a l conditions which can be encountered during tra n sp o rts .

C - 2 . 4 . 4 . In the c a s e o f ir ra d ia te d n u c le a r fu e l, th at fu e l s h a ll be s to re d a t the point a t w hich the sh ip m en t i s to o r ig in a te fo r a period of tim e which w ill ensure that, when the sh ipĀ­ping co n ta in er is loaded with the fu el e lem en ts , the m a x iĀ­mum tem p eratu re reached by any fuel elem ent w ill be such that a l l p a r ts of the so lid fu el, cladding, co n ta in e r o r b u ilt-in neutron a b so rb e r w ill rem ain at le a s t 100Ā° C below th e ir re s p e c t iv e m e ltin g p o in ts . F o r th is evalu ation , no heat tr a n s fe r m edia sh a ll be assum ed to be p re sen t o ther than a i r in the c a s e of a dry loaded co n ta in e r , and o th er than s ta t ic w a ter (in te rn a l) and a ir (e x tern a l) in the c a s e of a wet loaded co n ta in erĀ® .

C -3 . O TH ER G EN ERA L PACKING REQ U IREM EN TS

C - 3 .1 . M in im u m s i z e o f p a c k a g eThe s m a lle s t e x te rn a l d im ension of the package sh a ll not be le s s than 10 cm .

C ~3. 2. S e c u r i t y s e a lThe outside of every Type A and Type B package sh a ll in Ā­co rp o ra te a fe a tu re such as a s e a l , w hich is not re a d ily b re a k a b le , and w hich, w hile in ta c t, w ill be ev id en ce that the p ackag e has not b een i l l i c i t ly opened.

C - 3 .3 . L im i t a t i o n o f c o n ta m in a t io n o f th e s u r f a c e o f p a c k a g e sT he n o n -fixed ra d io a ctiv e con tam in atio n on any e x te rn a ls u rfa ce of the package sh a ll be kept as low as p ra c tica b le and in no ca se sh a ll exceed the lev els laid down in Table IV, Annex I .

C~3. 4 . C a t e g o r i e s o f p a c k a g e sP ack ag es sh a ll be in one of the follow ing th ree ca te g o rie s :(a) C a teg o ry I - W H ITE when the d ose ra te of rad ia tio n

orig inating from the package does not exceed 0. 5 mr/h o r equ iv alent at any point on the e x te rn a l s u r fa c e of the pack age at any tim e during tra n sp o rt ;

6 Paragraphs C - 2 .4 .3 . (a), C -2 .4 .3 . (c), C -2 .4 .3 . (d) and C -2 .4 .4 . are provisionallyretained pending the results of further study by a group of experts in 1965/66.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 32: Regulations for the Safe Transport of Radioactive Materials

1 8 PART C

(b) C ateg o ry II - Y EL L O W when the lim it in (a) above is exceeded, or when the package belongs to F is s i le C lass II7 (w hether or not the lim it in (a) above is exceeded), and(1) T he d ose ra te of ra d ia tio n o r ig in a tin g fro m the

package does not exceed at any tim e during tra n s Ā­port:(i) 10 m r/h o r equivalent at any point on the e x Ā­

te rn a l s u rfa ce of the package; and (ii) 0 . 5 m r/h o r equ ivalent at a d is ta n ce of 1 m

fro m the c e n tre of the p ackage; and(2) The tr a n s p o r t index d oes not e x ce e d 0 .5 at any

tim e d u ring tr a n s p o r t .(c) C a teg o ry III - Y E L L O W when one of the lim its in (b)

above i s exceed ed ; and(1) T he d ose r a te o f ra d ia tio n o r ig in a tin g fro m the

package does not exceed at any tim e during tra n s Ā­port:(i) 200 mr/h o r equivalent at any point on the ex Ā­

te rn a l su rface of the package; and(ii) 10 m r/ h o r equ iv alen t at a d is ta n c e of 1 m

fro m the c e n tre of the p a ck a g e ; and(2) The tran sp o rt index does not exceed 10 at anytim e

during tran sp o rt.(d) T he l im its p r e s c r ib e d in ( c ) (1 )(ii) and (c )(2 ) m ay be

exceeded provided that the package is tran sp o rted as a fu ll load and in a c c o rd a n c e w ith the re q u ire m e n ts o f P a r t D r e le v a n t to th e m od e o f t r a n s p o r t u s e d .

C ~ 3. 5 . L a b e l l i n g an d m a r k in gC - 3 . 5 . 1 . E a c h packag e sh a ll b e a r two la b e ls w hich sh a ll con form

to the m odel given in P a r t E , F ig s . 2, 3 o r 4 acco rd in g to the ca te g o ry of that package. The la b e ls sh a ll be affixed to two opposite sides of the outside of the package.

C -3 . 5 . 2. E ach package of g ro ss weight in e x ce ss of 50 kg sh a ll have its g ro ss weight plainly and durably m arked on the outside of the package.

C -3 . 5. 3 . E ach package which conform s to a Type A packaging design sh a ll be p la in ly and d urably m arked on the ou tside of the package with "T y p e A " .

7 See C-5.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 33: Regulations for the Safe Transport of Radioactive Materials

PART C 1 9

F o r each package w hich con form s to a Type A packaging d esign and which contains m o re than 3 c of gam m a e m itĀ­ting ra d io a ctiv e m a te r ia l, the o u ter s u r fa c e of the s te e l containm ent v e s s e l o r , w h ere the containm ent v e s s e l is en clo sed by a rad ia tio n sh ield of m a te r ia l with a m eltin g point in e x c e s s of 8 1 5 Ā°C, the outer su rface of such shield sh a ll be p lain ly m arked by em bo ssin g , stam ping o r o th er m eans r e s is ta n t to the e ffe c ts of f ir e and w ater, with the t r e fo i l sy m b o l shown in P a r t E , F ig . 1 and the w ord "R A D IO A C TIV E" in le t te r s not le s s than 10 mm in height. E ach package w hich con form s to a d esign approved under C - 6 .2 . , except fo r C - 6 .2 .1 . , shall be plainly and durably m arked on the outside of the package with the identification m ark a llocated to that d esign by the com petent authority , a s e r ia l nu m ber, and in the c a s e of a Type B p ackaging d esig n , w ith "T y p e B " .Each package which conform s to a Type B packaging design sh a ll have the ou tsid e of the o u term o st re ce p ta c le 'w h ic h is re s is ta n t to the e ffe c ts of f ire and w ater plainly m arked by em b o ssin g , stam ping o r o th er m ean s r e s is ta n t to the e ffe cts of fire and water-, with the tre fo il sym bol in P a r tE ,F i g - 1 ā€¢C om pliance with the above req u irem en ts fo r labellin g and m a rk in g s h a l l b e th e r e s p o n s ib i l i ty o f th e c o n s ig n o r . S p e c ia l p r o v i s i o n sAny fe a tu res added to the package at the tim e of tran sp o rt which are not part of the package must not reduce the sa fe Ā­ty of the package.A package containing rad ioactive m a te ria l shall not contain any o th er item s excep t a r t ic le s and docum ents w hich a re n e c e s s a ry fo r the use of the rad io activ e m a te r ia ls . Such a r t ic le s and docum ents may be included provided that they w ill not produce any additional hazard due to reactio n with the rad ioactive contents.

ALTERN ATIVE PACKAGING ARRANGEMENTS FOR LOW SP EC IFIC ACTIVITY M ATERIALS

Up to the q u antities p e r package sp ecified in C - l . 1 . , low sp e c ific activ ity m a te r ia ls as defined in A -2 . 8. (a) and (b),

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 34: Regulations for the Safe Transport of Radioactive Materials

2 0 PART C

in o th er than liquid o r g aseo u s fo rm , s h a ll be exem pted fro m th e p ack ag in g re q u ire m e n ts un d er C - 2 . , e x ce p t C - 2 . 1 . 1 ., p rovided th a t:(a) They a re packed in stro n g in d u stria l p ackages which

w ill p rev en t any lo s s of con ten ts under n o rm al conĀ­d ition s of tra n sp o rt;

(b) In the c a s e of m a te r ia ls defined in A -2 . 8 . (b) in m a sĀ­s iv e solid fo rm , they a re packed so as to prevent m ovem ents of any kind w hich m ay ca u se a b ra s io n of the m a te r ia l; and in o th er so lid fo rm s they a re con Ā­tained in an in e r t m e ta l c o v e r o r o th er su b sta n tia l sh eath such that the s u r fa c e of the m a te r ia l is not exp o sed .

C -4 . 2. Low sp e c ific activ ity m a te r ia ls tran sp orted as a fu ll load sh a ll be exem pted fro m the req u irem en ts of C - l . to C~3. in clu siv e , except C -3 . 6 . , provided that e ith e r :(a) They a re packed in stro n g in d u stria l p ackages which

w ill p re v e n t any lo s s of con ten t un d er n o rm a l co n Ā­d itio n s o f t r a n s p o r t ; o r

(b) They a r e loaded into a v e h ic le , an inland w a te rc ra ft o r sea-g o in g v e s s e l in such a m anner that, under n orĀ­m al conditions of tra n sp o rt, th e re w ill be no leakage of the m a te r ia l ou tside of the v e h ic le , o r of the hold o r co m p artm en t of the inland w a te rc ra ft , o r of the p art of the sea -g o in g v e s s e l in which they a re loaded.

The m a te r ia ls defined in A - 2 .8 .(b ) in m assiv e solid form sh a ll be packed o r stowed so as to prevent m ovem ents of any kind which may cause abrasion of the m ateria l; in other solid fo rm s they shall be contained in an in ert m etal cover o r o th er su b stan tia l sheath so that the su rfa ce of the m aĀ­t e r ia l is not exp osed . W here the m a te r ia ls defined in A - 2 .8 . ( d ) co n ta in f i s s i l e m a te r ia ls the l im its sp e c ifie d under C - 5 . 1 . 2 . (a), (c) o r (d) s h a ll not be exceed ed p e r p ackage; o r p er load if they a re loaded in accord an ce with(b) above.

C - 5 . AD D ITIO N AL R E Q U IR E M E N T S F O R PA C K A G ESCONTAINING F IS S IL E M A T E R IA L S

C - 5 . 1 . G e n e r a l p r o v i s i o n sC - 5 ; 1 .1 . R a d io a c tiv e m a te r ia ls w hich a r e a ls o f i s s i l e m a te r ia ls

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 35: Regulations for the Safe Transport of Radioactive Materials

PART C 21

s h a ll be packed in a cco rd a n ce with the re q u ire m e n ts of C - 1 . .C - 2 . and C - 3 .

C - 5 . 1. 2. In addition, p a ck a g e s o f f i s s i le m a te r ia l s h a ll m e e t the requ irem ents laid down in this sectio n except for the ca se s sp ecified hereunder:(a) P a c k a g e s contain ing individ ually not m o re than 15 g

uranium -233, or 1 5 guranium -235, o r 15gplutoniu m -239 o r 15 g plutonium -241, o r 15 g of any com bination of th e se rad io n u clid es;

(b) P ack ag es of irra d ia te d o r u n irrad ia ted n atu ra l o r deĀ­pleted uranium , in any quantity;

(c) P a c k a g e s of hom ogeneous hydrogenous so lu tio n s o r m ixtu res, in which the only f is s ile m a te ria l presen t is :(i) u ran iu m -233 o r u ran iu m -235 and th e h yd rog en :

u ra n iu m -2 3 3 o r h y d rog en : u ra n iu m -2 3 5 a to m ic ra tio is g re a te r than 5200, corresponding to uran i- um -233 o r uranium -235 con cen tratio n in com m on aqueous solutions of le s s than 5 g/1, or

(ii) p lutonium , and the hyd rogen : plutonium ato m ic r a t io is g r e a te r than 7600 co rre sp o n d in g to a plutonium co n c e n tra tio n in com m on aqueous so lu tion of l e s s than 3. 5 g/1;

and provid ed that the m axim um q u a n tities o f f i s s i l e m a te r ia l p e r p ackag e do not e x ce e d :

fo r u ran iu m -235 - 800 g, fo r u ran iu m -233 - 500 g, fo r plutonium - 500 g .

If m o re than one f is s i le m a te ria l is involved, the ratio of hyd rogen ato m s to f i s s i l e a to m s s h a ll be g r e a te r than 7600 and in ad dition the m axim u m quantity of f i s s i l e m a te r ia l p e r p ackage s h a ll not e x ce e d 500 g;

(d) P a c k a g e s o f h om ogeneou s s o lu tio n s o r com p ou nd s, exclud ing m e ta llic ro d s , in w hich the only f i s s i l e m a te r ia l p re s e n t i s e n r ic h e d u ran iu m o f w hich the u ran iu m -235 con ten t does not e x ce e d 1% o f the to ta l w eight o f u ran iu m .

C - 5. 2 . G e n e r a l p r o v i s i o n s f o r n u c l e a r s a f e t yC -5 . 2. 1. A ll f i s s i le m a te r ia ls sh a ll be packed and shipped in such

a m anner that c r itic a lity cannot be reached under any fo re Ā­s e e a b le c ir c u m s ta n c e s o f t r a n s p o r t . In p a r t ic u la r th e fo llow ing c o n tin g e n c ie s s h a ll be c o n s id e re d :

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 36: Regulations for the Safe Transport of Radioactive Materials

22 PART C

(a) W ater leak in g into p a ck a g e s ;

(b) The lo ss of e ffic ien cy of b u ilt-in neutron ab so rb ers or m o d erato rs;

(c) P o ssib le rearrangem ent of contents into m ore reactive a r r a y s , e ith e r within the packaging o r as a re s u lt of lo s s from the packaging;

(d) R ed u ctio n of s p a c e s b etw een p a ck a g e s o r c o n te n ts ;

(e) P a ck a g e s b eco m in g im m e rs e d in w ater o r b u ried in snow;

(f) P a ck a g e s b eco m in g in term in g led .

C -5 . 2. 2. In addition for irrad iated nu clear fuel or unspecified fiss ilem a te ria l the following assum ptions shall be made:

(a) F o r ir r a d ia te d n u c le a r fu e l: n u c le a r fu e l fo r w hich the d eg ree of irra d ia tio n is not known and whose r e Ā­activ ity d e c r e a s e s with burn-up sh a ll be regard ed as u n irrad ia ted fo r c r i t ic a li ty co n tro l. If its re a c tiv ity in c re a se s with burn-up it sh a ll be regard ed as ir ra d iĀ­ated to the point of m axim um re a c tiv ity . The r e a c t i Ā­v ity of n u c le a r fu el, fo r w hich the d eg ree o f i r r a d i Ā­ation is known, m ay be a s s e s s e d a cco rd in g ly ;

(b) F o r unspecified f is s i le m a te r ia ls : for f is s i le m ateria ls such as resid u es or scrap where the enrichm ent, m ass, concentration , m oderation ra tio or density is not known o r cannot be identified , it sh a ll be assum ed that each p a ra m ete r that is not known has the value which gives the m axim u m r e a c t iv ity u n d er c re d ib le co n d itio n s.

C - 5 . 2 . 3. P a c k a g e s o f f i s s i l e m a te r ia ls , e x ce p t a s provided inC - 5 . 1. 2 . (a) to (d) s h a l l b e d iv id ed in to th e fo llo w in g :

(a) F i s s i le C la s s I: p ack ag e s w hich a re n u c le a rly sa fein any num ber and in any arran gem ent under a ll fo re Ā­see ab le c ircu m sta n ce s of tran sp o rt;

(b) F i s s i l e C la s s II: p ack ag es w hich in lim ite d num ber a re n u clearly sa fe in any arran gem en t under a ll fo re Ā­see a b le c ircu m sta n ce s o f tra n sp o rt;

(c) F is s i le C la ss III: p ackag es which a re n u cle arly sa fe by re a so n of s p e c ia l a rra n g em e n ts .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 37: Regulations for the Safe Transport of Radioactive Materials

PART C 2 3

C - 5. 3 . P r o v i s i o n s s p e c i f i c t o F i s s i l e C l a s s I p a c k a g e s C -5 . 3 . 1. The n u cle a r sa fe ty c r i t e r ia fo r C la ss I p ack ag es sh a ll be

as fo llow s:C -5 . 3 . 1 . 1 . F o r the individual p ack ag e :

(a) The contents of any sin gle package sh a ll be lim ited so that:(i) W h e re m a s s i s th e c o n tro llin g n u c le a r s a fe ty

fa c to r , the p e r m is s ib le valu e s h a ll not e x ce e d 80% o f the c r i t i c a l m a s s ;

(ii) w here dim ension is the contro lling n u clear safety fa c to r , the p e rm is s ib le value of each con tro llin g d im ension sh a ll not exceed 92% of the re sp e ctiv e c r i t i c a l d im ension;

(b) F o r the purpose of a sse ss in g com pliance with (a), the following conditions sh a ll be assum ed :(i) The contents are re -a rra n g e d in the m ost reactiv e

co n fig u ra tio n w hich it has b een d em o n stra ted could o ccu r i f the p ackage w ere su b je cte d to the te s ts sp e c ifie d in Annex IV , 1 -4 ;

(ii) T h e p a ck a g e is fu lly im m e r s e d in w a te r ; and(iii) U n le s s o th e rw ise s p e c if ic a l ly ap p roved by the

com p eten t au th o rity of th e co u n try in w hich the p ack ag e d esig n o r ig in a te s and th e co m p eten t au th o rity o f e a ch co u n try through o r in to w hich the package is to be tran sp o rted , w ater leak s into a ll void sp a ce s .

C -5 . 3 . 1 .2 . F o r an a sse m b ly of p a ck a g e s :E a ch p ackage sh a ll be com posed and packed so th at:(a) Any num ber of such packages in any arran gem en t and

when in te rm ix e d w ith any n u m b er o f o th e r F i s s i l e C la s s I p ack ag e s in any a rra n g em e n t is s u b c r it ic a l , assum ing that each package has been su b jected to the te s ts sp ecified in Annex IV , 1 -2 . ; and

(b) 250 such p ackag es when damaged sh a ll be s u b c r it ic a l i f a ssem b led in any con fig u ration under the optim um co n d itio n s o f in te r s p e r s e d hyd rogenou s m o d e ra tio n and c lo s e ly r e f le c te d on th r e e a d ja ce n t s id e s by the equivalent of w ater. F o r the p u rp oses of th is clau se the cond ition of a l l p ack ag es s h a ll be assu m ed to be that which it has been evaluated or dem onstrated could o c c u r i f e a ch p ack ag e w e re s u b je c te d to th e t e s t s s p e c if ie d in A nnex IV , 1 -2 . and 1 -4 .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 38: Regulations for the Safe Transport of Radioactive Materials

24 PART C

C - 5 . 3 . 2. T h e n u c le a r s a fe ty c r i t e r i a in C - 5. 3 . 1. above s h a ll be co m p lied w ith by one o f th e fo llow ing m eth o d s:(a) B y fo llow ing the s c h e m e o f c a lc u la tio n s p e c if ie d in

Annex III, I - 1 .1 . o r any other schem e that m ay be in Ā­co rp o ra ted th ere in ;

(b) B y com p ly ing w ith any p h y s ic a l m o d el in A jin ex III, 1 -2 .1 ., or with any other data that may be incorporated th erein ; or

(c) B y com plying w ith the s p e c if ic a tio n s o f any package design that m ay be in co rp o rated in Annex III, I - 3 .1 .

C -5 . 4, P r o v i s i o n s s p e c i f i c to F i s s i l e C la s s I I p a c k a g e s C -5 . 4 . 1. The n u c le a r sa fe ty c r i t e r ia fo r F i s s i le C la s s II p ackages

s h a ll be as fo llow s:C -5 . 4. 1. 1. Under norm al conditions of tran sp ort each package shall

not su ffe r m o re than 5% red u ction in volum e on the b a s is o f w hich n u c le a r sa fe ty has been a s s e s s e d . One way of d em onstrating com p liance with th is req u irem en t sh a ll be that.no m o re than th is red uction o ccu rs when the package is su b je cte d to the te s ts sp e c ifie d in Annex IV , 1 -2 . ;

C -5 . 4 . 1 .2 . F o r the individual p a ck a g e :(a) The contents of any sin gle package sh a ll be so lim ited

that:(i) W h ere m a s s is th e c o n tro llin g n u c le a r s a fe ty

fa c to r , the p e r m is s ib le valu e s h a ll not e x ce e d 80% of the c r i t i c a l m a s s :

(ii) W here dim ension is the controlling nu clear safety fa c to r , the p e rm iss ib le value of each controlling dim ension sh a ll not exceed 92% .of the resp ectiv e c r i t i c a l dim ension;

(b) F o r the purpose of a sse ss in g com pliance with (a), the following conditions sh a ll be assum ed:

(i) The contents are re -a rra n g ed in the m ost reactiveco n fig u ra tio n w hich it h as b een d em o n stra ted could occu r i f the package w ere su b jected to the te s ts sp ecified in Annex IV , 1 -4 .;

(ii) T he p ack ag e is fu lly im m e rs e d in w a te r ; and(iii) U n less o th erw ise s p e c if ic a lly approved by the

com petent au thority of the country in w hich the p ack ag e d esig n o r ig in a te s and th e com p eten t au th ority of e a ch cou ntry through o r into w hich th e p ack ag e i s to be tra n s p o r te d , w a te r le a k s in to a l l vo id s p a c e s .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 39: Regulations for the Safe Transport of Radioactive Materials

PART C 25

C - 5 . 4 . 1 . 3 . F o r an a s s e m b ly of p a c k a g e s :An "a llow ab le n u m b er" sh a ll be d erived fo r each F is s i le C lass II package. The allow able number of packages shall sa tis fy a ll of the following conditions:(a) F ive tim es the allow able number of undamaged packages

sh a ll be s u b c r it ic a l when stacked together in any conĀ­figuration, without in te rsp erse d m oderation assum ing c lo s e re f le c t io n on a ll s id e s of the s ta c k by w ater o r i ts e q u iv a le n t. F o r th is p u rp o se 'u nd am aged ' s h a ll m ean the conditions on the b a s is of which the n u clear sa fe ty is a s s e s s e d .

(b) Tw ice the allow able num ber of damaged packages shall be s u b c r it ic a l if assem bled in any configuration under the optim um con d ition s o f in te rs p e r s e d hydrogenous m o d eratio n , and c lo s e ly re f le c te d on a ll s id e s of the s ta c k by w a ter o r i ts eq u iv a len t. F o r the p u rp o ses o f th is c la u s e , the cond ition o f a ll p ack ag es sh a ll be assum ed to be that which it has been evaluated or deĀ­m onstrated could occu r if each package were submitted to the t e s t s s p e c if ie d in A nnex IV , 1 -2 . and 1 -4 . M o d e ra tio n due to w a te r in le a k a g e c o n s is te n t w ith te s t r e s u lts s h a ll be a ssu m e d .

C -5 . 4 . 2. C om pliance with the s p e c ifica tio n s of any package design in A nnex III, I I - 1. , s h a ll be one m ethod o f m eetin g the F i s s i l e C la s s II n u c le a r s a fe ty c r i t e r ia .

C -5 . 5. P r o v i s i o n s s p e c i f i c to F i s s i l e C la s s II I p a c k a g e sC -5 . 5. 1. A ll packages of f is s i le m a te r ia l in quantities or under conĀ­

d ition s w hich do not fa ll under C -5 . 1. 2. (a) to (d) and do not m eet a ll the sp ecifica tio n s of F is s i le C lass I or F is s i le C lass II, sh all be F is s i le C lass III packages.

C -5 . 5. 2. Shipm ent of F is s i le C la ss III packages sh a ll be made only by s p e c ia l a rra n g em e n t, in a cco rd a n ce with the re le v a n t p ro v is io n s of C -6 . 5.

C -5 . 5. 3. Such shipm ents sh a ll be made under conditions which m eet ^ the g en era l req u irem en ts of C -5 . 2. 1.

C -5 . 5. 4. When other consignm ents m ust not be shipped with F is s i le C lass III packages, a sp ecific re s tr ic t io n shall be provided in the sp e c ia l arran gem ent and an instru ction to that e ffect issu ed with the tran sp o rt docum ents.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 40: Regulations for the Safe Transport of Radioactive Materials

2 6 PART C

C -6 . A D M IN ISTRA TIVE R EQ U IR EM EN TS

C -6 . 1. A p p r o v a l o f c a p s u le d e s ig n f o r s p e c ia l f o r m r a d io a c t i v em a t e r i a l s u n d e r A - 2 . 13. (b)T h e d esig n o f the ca p su le s h a l l r e q u ir e th e ap p ro v al of the com petent authority of the country in which the capsule design o rig in a tes.T h e co m p eten t a u th o rity s h a l l e s ta b l is h a c e r t i f i c a t e s ta tin g that the approved d esign m e e ts the re q u ire m e n ts of th ese regu lations and specifying the nature of the rad io Ā­activ e m a te r ia l which can be so encapsulated.

C - 6. 2. A p p r o v a l o f p a c k a g in g and p a c k a g e d e s ig nE x cep t in the c a s e of a packaging o r p ackage d esign co n Ā­form ing to the detailed sp ecifica tion s published in Annex III, I - 3 r l -.~ and-H-A^~and in A nnex V the fo llow ing ap p rov als s h a ll be re q u ire d :

C - 6 . 2 .1 . A p proval o f p ack ag e d esig n fo r p .yrophoric ra d io a c tiv e m a te r ia lThe design of ap ackage fo r pyrophoric rad io activ e m a te r ia l s h a ll re q u ire the ap p rov al o f the com p eten t au th o rity of the country in which the design o rig in ates. The com petent authority shall e stab lish a ce rtifica te stating that the design has been approved and sp ecify in g by d eta iled d escrip tio n the m a te r ia l fo r w hich the p ackage can be used .

C -6 . 2 . 2. A pproval of Type B packaging design(a) A Type B packaging design sh a ll re q u ire the approval

of the com petent authority of the country in which the packaging design o r ig in a te s .

(b) An application fo r approval sh a ll include:A q u a lita tiv e d e scr ip tio n o f the p ro p osed co n ten ts w hich p a r t ic u la r r e fe r e n c e to th e ir p h y s ic a l and c h e m ic a l s ta te s , and the n atu re o f th e ra d ia tio n em itted ;A d etailed d escrip tio n of the design including co m Ā­p lete engineering drawings and schedules of m ateria ls and methods of construction to be used;A sta te m e n t of the te s t s w hich have been done and th e ir r e s u lts , o r e v id e n ce b a se d on c a lc u la tiv e m eth o d s th a t the p ack ag in g d esig n is ad equate to m e e t the re q u ire m e n ts , o r o th er ap p ro p ria te e v iĀ­d en ce; and

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 41: Regulations for the Safe Transport of Radioactive Materials

PART C 2 7

The d ra ft o p era tin g in s tru c t io n s th at the d e s ig n e r s h a ll g ive to the u s e r s a f te r ap p rov al.

(c) The com petent au th ority sh a ll e s ta b lis h a c e r t i f ic a te s ta tin g th at the approved d esign m e e ts the r e q u ir e Ā­m en ts of th e se reg u la tio n s and sh a ll a ttr ib u te to the d esign an id e n tifica tio n m a rk . The c e r t i f ic a te sh a ll specify any re s tr ic t io n s on the nature of the perm itted contents of the packaging and shall include any sp ecific instruction s on its use.

(d) The m an u factu rer, co n sig n o r o r u s e r of an approved packaging design shall be prepared to provide the com Ā­petent au th ority with com p lete c e r t i f ic a t io n that the c o n s tr u c t io n a l m eth o d s and m a te r ia ls u se d fo r th e co n stru ctio n of that packaging a re in acco rd an ce with the approved d esig n r e q u ir e m e n ts . The co m p eten t au th o rity m ay c a r r y out in sp e ctio n of the p ackaging during co n stru c tio n .

C - 6 .2 .3 . Approval of packaging design fo r larg e rad ioactive sou rces(a) Package not requ iring sp e cia l precautions en rou te

excep t as m ay be req u ired in the event of accid en t or unexpected delay:

(i) The design sh all req u ire the approval of the com Ā­petent authority of the cou ntry in which the packaging design o r ig in a te s ;

(ii) An a p p lica tio n fo r a p p ro v a l s h a l l in c lu d e , in ad dition to th e in fo rm a tio n re q u ire d in (b) of C -6 . 2. 2. above, a s p e c if ic d efin ition o f the p ro Ā­posed contents and evidence to d em on strate that the p ackag in g d esig n m e e ts the ad d itio n al r e Ā­q u ire m e n ts o f the re g u la tio n s fo r la r g e ra d io Ā­a c tiv e s o u r c e s .

(iii) The com petent authority sh a ll e s ta b lis h a c e r t i Ā­fica te stating that the approved design m eets the requ irem en ts of these regulations and sh a ll a t tr i Ā­bute to the d esign an id e n tifica tio n m a rk . The c e r t i f ic a t e s h a ll inclu d e a d eta iled d e s c r ip tio n of the perm itted contents, as w ell as any sp e c ific in stru ctio n s re la tin g to the use of th e packaging.

8 i . e . m e e ts th e a p p lic a b le p a c k a g in g req u irem en ts w ithout hum an in te rv e n tio n ,su c h

as p e r io d ic a l v en tin g or c h e ck in g o f te m p e ra tu re .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 42: Regulations for the Safe Transport of Radioactive Materials

2 8 PART C

(b) P a ck ag e re q u irin g s p e c ia l p re cau tio n s en r o u t e even in the ab se n ce of acc id en t o r unexpected delay.The sam e requ irem ents as in (a) above sh a ll be applied. In addition:

(i) The c e r t i f ic a te sh a ll sp e cify the sp e c ia l p re c a u Ā­tio n s en r o u te w hich a re needed; and

(ii) The design sh a ll req u ire the approval of the com Ā­petent au thority in a ll co u n trie s through o r into w hich the p ackage is to be tra n sp o rte d . Such ap p rov al m ay be in d ica ted by v a lid a tio n of the c e rtif ic a te established by the com petent authority of the country in which the packaging design o r ig iĀ­nates.

C - 6 . 2 . 4 . A p p rov al o f F i s s i l e C la s s I. II and III p ack ag e d esig n s(a) The design shall requ ire the approval of the com petent

au th ority of the cou ntry in w hich the package d esign o r ig in a te s .

(b) An a p p lica tio n fo r a p p ro v a l s h a l l in clu d e a l l in fo r Ā­m ation n e c e s s a r y to s a t is fy the com p eten t au th ority that the design m eets the req u irem en ts of the relevan t p art of th ese regu lations.

(c) The com petent au th ority sh a ll e s ta b lis h a c e r t i f ic a te s ta tin g th at the approved d esig n m e e ts the r e q u ir e Ā­m en ts of th e se reg u la tio n s and sh a ll a ttr ib u te to that d esign an id e n tifica tio n m a rk . I f the p e r m is s ib le contents exceed the activ ity lim its sp ecified in C - l . 1., the c e r t i f i c a t e s h a l l in d ica te th a t th e d esig n h as in p a r t ic u la r been approved in acco rd an ce with the p ro Ā­v is io n s of C -6 . 2. 2. and, w here ap p rop riate , C -6 . 2. 3. above.The c e r t if ic a te sh a ll include:

for F is s i le C lass I p ackages: a detailed d escrip tion of the p e rm iss ib le contents;for F is s i le C lass II p ackages: a detailed d escrip tion of the p e r m is s ib le co n ten ts and the co rresp o n d in g a llow able n u m b ers ;for F is s i le C lass III packages: a detailed description of the individual consignm ent;

and in e v e ry c a s e , any in s tru c t io n s th at m ay be n eĀ­c e s s a r y fo r th e u se of the p ackag in g .

(d) In ad dition , e x ce p t in th e c a s e of F i s s i l e C la s s I

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 43: Regulations for the Safe Transport of Radioactive Materials

PART C 2 9

packages com plying with the req u irem en ts of Annex III, 1-2 . 1. together with p e rm issib le contents in accordance w ith th e a sso .c ia te d T a b le s I to X , th e d esig n s h a l l re q u ire the approval of the com petent au thority of a ll co u n tr ie s through o r into w hich th e p ack ag e is to be tran sp orted . Such approvals may be indicated by v a liĀ­dation of the c e r t i f ic a te e sta b lish e d by the com petent authority of the country in which the packaging design o r ig in a te s .

C -6 . 3. A p p r o v a ls f o r s h ip m e n t a n d p r i o r n o t i f i c a t i o nApprovals sh a ll be requ ired and notification sh a ll be made in the following c a s e s :(a) Shipm ent of la rg e rad io activ e so u rce s including those

which a re a lso F is s i le C la ss I or II p ack ag es, not r e Ā­q u irin g s p e c ia l p re ca u tio n s en r o u t e e x ce p t a s m ay be requ ired in the event of accident or unexpected delay.

(i) T he sh ip m ent s h a ll re q u ire the ap p ro v al of the com p eten t au th o rity of the co u n try o f o r ig in of th e sh ip m en t; and

(ii) R equests for approval shall include a ll inform ation n e c e s s a r y to d em o n stra te co m p lia n ce w ith the requ irem ents of the relevan t p arts of these reguĀ­la tio n s and sh a ll in d icate the proposed mode of tra n sp o rt , the roffte , and, a s a p p ro p ria te , any s p e c ia l load in g , unloading and o th e r handling p ro c e d u re s and the s p e c ia l p re c a u tio n s to be taken in the event of accident or unexpected delay.

( iii) Upon ap p rov al o f a sh ip m en t the com p eten t au th o rity s h a l l is s u e a c e r t i f ic a t e a u th o riz in g the shipm ent, specify ing the conditions to be obĀ­served and confirm ing that no sp ecia l precautions en r o u t e a re needed excep t as m ay be re q u ired in th e e v e n t o f a c c id e n t o r u n e x p e c te d d e la y .

(iv) P r i o r a r r a n g e m e n ts s h a l l be m ad e w ith e a c h c a r r i e r who is to t r a n s p o r t th e s h ip m e n t.

(v) P r io r n o tifica tio n of the shipm ent sh a ll be given to the com petent authority in a ll cou ntries through o r into w hich the shipm ent is to be tran sp o rte d .

(b) Shipments of F is s i le C lass III packages or of packages containing la rg e rad io activ e so u rce s (including those which are also F is s ile C lass I or II packages)requ iring

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 44: Regulations for the Safe Transport of Radioactive Materials

30 PART C

s p e c ia l p re ca u tio n s en r o u t e even in the a b se n ce of a cc id e n t o r u n exp ected d elay :The sam e requ irem ents as in (a) above shall be applied except that:

(i) The request for approval shall indicate in addition the p ro p osed s p e c ia l p re ca u tio n s to be tak en en route-, and

(ii) The shipm ent s h a ll re q u ire the ap p roval of the com petent au thority of a ll co u n trie s through o r into w hich the sh ip m en t i s to be tra n s p o rte d . Such ap p ro v a ls m ay be in d ica ted by v a lid a tio n o f th e c e r t i f ic a t e e s ta b lis h e d by th e com p eten t au th o rity of the cou n try in w hich the sh ipm ent o r ig in a te s .

C -6 . 4. In fo r m a t io n to b e m a d e a v a i l a b l e to c a r r i e r sT h e p a r t ic u la r s o f th e co n sig n m e n t and th e c e r t i f ic a t e s re fe r re d to in th is sectio n need not n e c e s s a r ily accom pany the consignm ent to which they re la te ; they sh a ll, how ever, be available at loading, unloading and at any transhipm ent, p re fe ra b ly in advance. Such in form ation and c e r t i f ic a te s sh a ll be w ritten in the languages deemed n e c e s s a ry by the c a r r ie r or the au th orities concerned .

C -6 . 4 .1 . C o n sig n o r's ce r tifica tio nWhen tra n sp o rt docum ents a re issu ed , the goods sh a ll be en tered th e re in as "rad io activ e m a te r ia l" . The tran sp ort d ocu m ents s h a ll inclu de a c e r t i f ic a t e under the o r ig in a l o r stam p ed fa c s im ile s ig n a tu re of the co n s ig n o r o r h is duly a u th o rized ag en ts in th e fo llow ing te r m s :

This is to c e rtify that the above-nam ed goods are p roĀ­p e rly d escrib ed and a re packed and m arked in a c c o r Ā­dance with the applicable regulations and are in proper condition fo r tran sp o rt.

C -6 . 4 . 2. P a r t ic u la r s of consignm ent(a) T he Group o r G roups of the rad io n u clid es contained

in th e ra d io a c tiv e m a te r ia l;(b) The name of the rad ioactive m a te ria l, and a description

o f i t s p h y s ic a l and c h e m ic a l fo rm , o r w h eth er the m a te r ia l i s in s p e c ia l fo rm ;

(c ) T h e a c t iv ity o f th e r a d io a c t iv e m a te r ia l in c u r ie s ;(d) The category of thepackage, i. e. I-W H ITE, II-YELLO W ,

III-Y EL L O W ;

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 45: Regulations for the Safe Transport of Radioactive Materials

PART C 3 1

(e) The "tran sp o rt index" (ca teg o ries II- an d lll-Y E L L O W only);

(f) The type of packaging (ind ustrial, A or B );(g) F o r a consignm ent of f is s i le m a te ria l:

(i) If exem pted under C -5 . 1. 2. the quantity in g ram s, th e c o n c e n tra tio n and the e n r ich m e n t in u235 w h ere a p p ro p ria te ; and

(ii) In o th er c a s e s , the f i s s i l e c la s s of the p ack ag e . C -6 . 4 . 3. A dditional c e r t i f ic a t io n

A copy of the c e r t i f ic a te s corresp o n d in g to the approvals r e q u ire d , a s a p p ro p ria te , u n d er C - 6 . 1 . , C - 6 . 2 . 1 . ,C -6 . 2. 2 . , C -6 . 2 . 3 . , C -6 . 2. 4. and C -6 . 3. sh a ll be p roĀ­vided. An e x tra c t from the c e r tif ic a te indicated in C -6 .2.2.(c ) co n ta in in g th e id e n tif ic a tio n m a rk a ttr ib u te d by the com petent authority to the approved design may be accepted in p lace of the full ce r tif ic a te of approval.

C - 6 . 5. S p e c i a l a r r a n g e m e n t sA co n sig n m en t o f ra d io a c tiv e m a te r ia ls w hich d oes not s a t is f y a l l re le v a n t p a r ts o f th e s e re g u la tio n s m ay only be tra n sp o rte d w ith th e p r io r ap p ro v al o f the com p eten t a u th o ritie s of a ll co u n trie s a ffec te d by the m ovem ent. In su ch a c a s e the com p eten t au th o rity o r a u th o ritie s sh a ll im p o se con d ition s adequate to e n s u re th a t th e tra n s p o r t o f the co n sig n m e n t s h a l l b e no l e s s s a fe than i f a l l the re le v a n t p ro v is io n s o f th e s e re g u la tio n s had b e e n c o m Ā­p lie d w ith.

C - 7 . A D D IT IO N A L R E Q U IR E M E N T F O R D E L I V E R Y O F AL A R G E R A D IO A C T IV E S O U R C E T O T R A N S P O R T

P r io r to sh ip m en t, a p ack ag e co n ta in in g a la r g e r a d io Ā­a c tiv e s o u r c e s h a l l be h e ld by th e c o n s ig n o r u n til the tem p eratu re of the system has reached equilibrium un less it h as b een d em o n stra ted to the s a t is fa c t io n o f the co m Ā­petent authority that its equilibrium conditions w ill sa tisfy the re lev an t req u irem en ts of C -2 . 4.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 46: Regulations for the Safe Transport of Radioactive Materials

P A R T D - REGULATIONS CONCERNING STORAGE AND CARRIAGE

D - l . SEGREG ATIO N O F RADIOACTIVE M A TERIA LS FROM PERSO N S AND FILM S

In the co u rse of tra n sp o rt, rad io activ e m a te r ia ls , except in ca te g o ry I - W HITE p ack ag es, sh a ll be kept sep arated from living accom odation, from regu larly occupied working sp a ce s and fro m sp a ce s that m ay be continu ally occupied by p a s s e n g e r s o r the p u blic so th at th e re q u ire m e n ts of A -4. 1. a re ob served . They sh a ll be kept sep arated from undeveloped photographic film s or p la tes so that th ese are not exposed to m o re than 10 m r. The app rop riate s e g r e Ā­gation d istan ces sh a ll be d erived using T a b le s V to V E in Annex I .

D -2 . STO RA G E

D -2 . 1. T he nu m ber o f ca te g o ry I I - and III - Y E L L O W p ack ag ess to r e d in any one p la c e , su ch a s a te r m in a l build ing o r s to re ro o m , sh a ll be lim ite d so that the sum of the t r a n s Ā­p o rt in d e x es on th e ir la b e ls does not e x ce e d 50, u n le ss those packages are in groups, none of which contains tra n s Ā­port indexes, the sum of which is ā€™ in e x c e s s of 50 and each group is handled and sto red not c lo s e r to any other group than 6 m. W here th is co n tro l is not e ffected by re fe re n ce to tran sp ort indexes, th ere sh a ll be not m ore than 100 ca te Ā­gory II or 5 category III packages in any one group. W here p a ck a g e s o f both c a te g o r ie s a r e p re s e n t , 1 c a te g o ry III p a ck ag e s h a l l be ta k e n as eq u iv a len t to 20 p a ck a g e s of c a te g o ry II.

D -2 . 2 . P a ck a g e s o f ra d io a ctiv e m a te r ia ls sh a ll not be s to re d inth e sa m e p la c e as d angerou s goods w ith w hich com m onload ing i s p ro h ib ited in D -3 . 1 .2 . below .

D -3 . C A R R IA G E

D - 3 . 1. G e n e r a l r e q u i r e m e n t sD -3 . 1. 1. C onsignm ents of ra d io a c tiv e m a te r ia ls sh a ll be s e c u re ly

stow ed.

3 2

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 47: Regulations for the Safe Transport of Radioactive Materials

PART D 33

D -3 . 1. 2. P a ck a g e s of ra d io a ctiv e m a te r ia ls s h a ll not be loaded in the sam e v e h ic le , a i r c r a f t o r hold o r co m p artm en t o f an inland w ater c ra f t or p art of a seagoing v e s s e l as dangerĀ­ous goods w hich, on the b a s is o f th e re le v a n t tra n s p o r t r e g u la tio n s , cou ld a d v e rs e ly a ffe c t th e in te g r ity o f the p ackaging o f th e s e ra d io a c tiv e m a te r ia ls u n d er a cc id e n t ā– conditions. C o n sid eratio n sh a ll in p a r t ic u la r be given to

. such dangerous goods as exp losive , in flam m able, c o rro s iv e , oxidizing, spontaneously com bu stib le m a te r ia ls and g a ses co m p ressed , liquefied or d issolved under p re s s u re .

D -3 . 1. 3. C ategory I - W HITE, II - o r III - Y ELLO W packages sh a ll not be c a r r ie d in co m p artm en ts occu pied by p a s s e n g e rs , excep t th o se e x c lu s iv e ly re s e r v e d fo r c o u r ie r s sp e c ia lly au thorized to accom pany such p a ck ag es .

D -3 . 1 . 4. T h e n u m ber of c a te g o ry II - o r III - Y E L L O W p a ck a g e s in any one v e h ic le , a ir c r a f t o r inland w ater c ra f t sh a ll be lim ite d so that the sum of the tra n sp o rt in d exes does not exceed 50. F o r seagoing v e s s e ls , see D -3 . 5. W here th is co n tro l is not e ffe cte d by re fe re n c e to tra n sp o rt in d exes, th e r e s h a l l be not m o re than 100 c a te g o ry II o r 5 c a t e Ā­gory III p ackages. W here packages of both ca te g o rie s are p r e s e n t , 1 c a te g o ry III p ack ag e s h a l l be ta k e n a s e q u iĀ­v a le n t to 20 p a ck a g e s o f c a te g o r y II.

D -3 . 1. 5. In the c a s e o f fu ll load o f low s p e c if ic a c tiv ity m a te r ia ls in acco rd an ce with C -4 . 2. the e stim ated to ta l rad io activ e content in any one v e h ic le or any hold or com partm ent of an inland w a te rc ra ft or p art of a seagoing v e s s e l sh a ll not exce e d :(a) 0. 1 c of rad ionu clid es of Group I; or(b) 5 c of rad ion u clid es of Group II; or(c) 250 c of rad ion u clid es of Group III; or(d) 250 c of rad ion u clid es of Group IV.If the m a te r ia ls contain radionuclides belonging to d ifferent groups, the sum of

(the num ber of c u r ie s in Group I) X 10+ (the number of cu rie s in Group II) X 1/5+ (the num ber of cu rie s in Group III) X 1/250+ (the number of cu rie s in Group IV) X 1/250 shall not

exceed 1.D -3 . 1 . 6 . R e q u ire m e n ts r e la t in g to th e d e co n ta m in a tio n o f c o n Ā­

v e y a n c e s

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 48: Regulations for the Safe Transport of Radioactive Materials

3 4 PART D

(a) If th ere is evidence of leakage, a survey of the package, the conveyance, the ad jacent loading or unloading a re a and a ll o th er m a te r ia l w hich has b een c a r r ie d in the conveyance sh a ll be made to a s s e s s the extent of conĀ­tam in atio n . The con v ey an ce and equipm ent s h a ll be d ealt with as provided fo r under (c) below . L eaking p ackages m ust not be forw arded until re p a ire d o r r e Ā­conditioned;

(b) C o n vey an ces and equipm ent u sed ro u tin e ly fo r the ca rr ia g e of rad ioactive m a te ria ls sh a ll be p eriod ically checked to d eterm ine the le v e l of contam ination. The frequency of such checks sh a ll be re la ted to the l ik e liĀ­hood of contam ination and the extent to which rad io Ā­activ e m a te r ia ls a re c a r r ie d .

(c) E xcep t as provided fo r in (d) below , any conveyance, equipm ent, o r p art th e re o f w hich has b eco m e co n ta Ā­m inated in the co u rse of c a r r ia g e of rad io activ e m a te r ia ls sh a ll be decontam inated as soon as p o ssib le by a qualified p erson , and sh all not be re -u se d u n less:

(i) T he to ta l co n tam in atio n (fixed and n o n -fix e d ) is below the le v e ls sp e c ifie d in T a b le IV , A nnex I; o r

(ii) T h e n o n -fix e d co n tam in atio n is below the le v e ls specified in Table IV, Annex I, and the conveyances, equ ip m ent o r p a r t th e r e o f have b ee n o th e rw ise d e c la re d sa fe by the ap p ro p ria te com p etent au th ority ; and

(d) In the c a s e of conv eyances o r com p artm en ts used for the tra n sp o rt of low sp e c ific activ ity m aterial^/in fu ll load, th e se con v eyan ces and co m p artm en ts sh a ll not be used fo r other goods until decontam inated as sp e ciĀ­fied in (c) (i) or (c) (ii) above.

D - 3 . 2. A d d i t i o n a l r e q u i r e m e n t s r e l a t i n g to t r a n s p o r t b y r a i lD -3 . 2 . 1. R a il v e h ic le s c a r ry in g ca te g o ry I - W H ITE o r I I - o r I I I '

Y E L L O W p a ck a g e s s h a ll d isp lay th e p la c a rd show n in P a r t E , F ig . 5 on e a ch of th e two e x te r n a l la t e r a l w a lls .

D -3 . 2 . 2 . In the c a s e o f fu ll lo a d s:(a) T he ra d ia tio n d ose r a te s h a ll not e x ce e d

(i) 200 m r/h o r equ ivalent at any re a d ily a c c e s s ib le su r fa ce of the r a i l v e h ic le ; and

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 49: Regulations for the Safe Transport of Radioactive Materials

PART D 35

(ii) 10 m r/ h o r equ ivalent at 2 m fro m any e x te rn a l s u r fa c e o f the r a i l v e h ic le ;

(b) The lim its under D -3 . 1 .4 . sh a ll not apply. In the ca se o f F i s s i l e C la s s II p a ck a g e s , how ever, the fu ll load s h a l l not in clu d e m o re than th e a llo w ab le n u m b erS ;

(c) T he r a i l v e h ic le s h a ll d isp lay th e p la c a rd show n in P a r t E , F ig . 5 on e a c h o f th e two e x te r n a l l a t e r a l w a lls .

D - 3 . 3. A d d i t io n a l r e q u i r e m e n t s r e l a t i n g to t r a n s p o r t b y r o a dD -3 . 3 . 1. E x c e p t fo r th e d r iv e r and a s s is ta n t s , no o th e r p e rs o n s

s h a l l be c a r r ie d in ro ad v e h ic le s c a r r y in g r a d io a c tiv e m a te r ia ls .

D -3 . 3 . 2. Road v e h ic le s c a r ry in g ca te g o ry I - W H ITE - o r II - o r III - Y E L L O W p ack ag e s s h a ll d isp lay the p la c a rd shown in P a r t E , F ig . 5 on each of the two e x te rn a l la te r a l w alls.

D -3 . 3. 3. In the c a s e of fu ll lo ad s:(a) The rad ia tio n dose ra te sh a ll not exceed

(i) 200 m r/h or equivalent at any read ily a c c e ss ib le su rfa ce of the road v e h ic le ; and

.(ii) 10 m r/h o r equ ivalent at 2 m fro m any e x te rn a l s u r fa c e of the ro ad v e h ic le ;

(b) The lim its under D -3 . 1. 4. sh a ll not apply. In the ca se of F i s s i l e C la s s II p a ck a g e s , h ow ever, the fu ll lpad s h a l l not in clu d e m o re than th e a llo w ab le n u m b er9 ;

(c ) T h e ro ad v e h ic le s h a l l d isp lay the p la c a rd show n in P a rt E , F ig . 5 on each of the two extern al la te ra l w alls.

D - 3 . 4. A d d i t i o n a l r e q u i r e m e n t s r e l a t i n g to c a r r i a g e b y i n la n d w a te r c r a f tThe p ro v isio n s under th is heading w ill be issu ed s e p a ra Ā­te ly in due co u rse .

D -3 . 5. A dd i t io na l r e q u i r e m e n t s i-elating to c a r r ia g e b y sea go ing v e s s e l s

T he n u m ber o f ca te g o ry II - o r III - Y E L L O W p ack ag e s

* S e e C - 5 . 4 . 1 . 3 . In th e c a s e w here th e c o n sig n m e n t is m a d e up o f p a ck a g e s o f d iffe re n t

a llo w a b le num bers th e m a x im u m nu m b er o f p a ck a g e s tran sp orted in a fu ll lo ad sh a ll b e such

th a t th e fo llo w in g fo rm u la is sa tis f ie d :

n l n2 n 3 , ā€žā€” +.ā€” + ā€” + ...................... e t c . sh a ll n o t e x c e e d 1 .N l N2 N3

In th is fo rm u la n l , n 2 , n 3 a re th e n um bers o f p a ck a g e s for w h ich th e a llo w a b le num bers are

N l , N 2 , N3 . . . r e s p e c t iv e ly .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 50: Regulations for the Safe Transport of Radioactive Materials

3 6 PART D

sh a ll n orm ally be so lim ited that the sum of the tran sp o rt indexes indicated on them sh a ll not exceed 200, provided that no group of such p ack ag es sh a ll co m p rise tra n sp o rt in d exes the sum of which e x ce e d s 50, and that each such group sh a ll be handled and stowed not c lo s e r to any other group th an 6 m . W h ere th is c o n tro l is not e ffe c te d by re fe r e n c e to tra n sp o rt in d e x es , th e re s h a ll be not m o re than 100 ca teg o ry II or 5 ca teg o ry III packages in any one group. W here p ack ag e s of both c a te g o r ie s a re p re s e n t,1 ca te g o ry III package sh a ll be taken as equ ivalent to 20 p ack ag es of ca te g o ry II. P r io r ap p roval sh a ll be obĀ­ta in ed fro m the ap p ro p ria te com p eten t au th o rity i f it is proposed to convey in any one ship packages such that the sum of the tran sp ort indexes indicated on them exceeds 200.

D -3 . 6. A d d it io n a l r e q u i r e m e n t s r e l a t i n g to c a r r i a g e b y a i rD -3 . 6 . 1. T ran sp o rt of low sp e cific activ ity m a te ria ls in accordance

with C -4 . 2. sh a ll not be p erm itted .D -3 . 6. 2. F u ll loads of larg e rad ioactive so u rces in accord ance with

C -3 . 4. (d) s h a ll be c a r r ie d on c a rg o a i r c r a f t only . In re sp ect of such consignm ents the lim its of D -3 . 1. 4. sh all not apply . - H ow ever, in the c a s e o f F i s s i l e C la s s II p a ck a g e s , the fu ll load s h a ll not inclu d e m o re than the a llo w ab le n u m b er.9

D -3 . 7. T r a n s p o r t , b y p o s t ,D -3 . 7. I.- A consignm ent of rad ioactive m a te ria ls that conform s with

P a r t B of th e se reg u la tio n s m ay be accep ted fo r in te rn a l m ovem ent by n ational p o sta l a u th o rities , s u b je c t to such additional re q u irem en ts as those au th orities may p re s c r ib e .

D -3 . 7. 2. A consignm ent of rad ioactive m ate ria ls that conform s with P a r t B -o f th e s e re g u la tio n s m ay be a c c e p te d fo r in te r Ā­n ation al m ovem ent by p ost s u b je c t, in p a r t ic u la r , to the follow ing ad ditional re q u ire m e n ts :10

8 S e e C - 5 . 4 . 1 . 3 . In th e c a s e w h ere th e c o n s ig n m e n t is m a d e up o f p a ck a g e s o f d if fe re n t

a llo w a b le n um bers th e m a x im u m n u m b er o f p a c k a g e s tran sp orted in a fu ll lo ad sh a ll b e such

th a t th e fo llo w in g fo rm u la is sa tis fied :

n l n2 n3 , ā€ž , ,ā€” + ā€” + ā€” + .............. e t c . sh a ll n o t e x c e e d 1 .N l N 2 N3

In th is fo rm u la n l , n 2 , n 3 a r e th e num bers o f p a ck a g e s for w h ich th e a llo w a b le num bers are

N l , N 2 , N3 . . . r e s p e c t iv e ly .

10 T h o se re q u irem e n ts are p rescrib ed by th e C o n v en tio n o f th e U n iv ersa l Postal U n io n ,

w ith e f f e c t from 1 J a n . 1 9 6 6 .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 51: Regulations for the Safe Transport of Radioactive Materials

PART D 37

(a) It s h a l l be d ep osited with the p o s ta l s e r v ic e only by c o n s ig n o rs au th orized by the n a tio n a l com p eten t au th ority ; and

(b) It s h a l l b e d esp atch ed a s a le t t e r - p o s t ite m b y th e q u ick e s t ro u te , n o rm a lly by a i r ; and

(c) It s h a ll c a r r y on the outside a white la b e l b earin g the words "rad io activ e m a te r ia ls " , which sh a ll be cro sse d out i f the packaging is retu rned empty; aiid

(d) It sh a ll c a r r y on the outside the nam e and ad d ress of the co n s ig n o r w ith th e re q u e s t th at th e co n sig n m en t b e re tu rn e d in the c a s e of n o n -d e liv e ry ; and

(e) The nam e and ad d ress of the con sign or and the content of the consignm ent s h a ll be in d icated on the in te rn a l packaging .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 52: Regulations for the Safe Transport of Radioactive Materials

P A R T E - L A B E L S AND P L A C A R D S

L a b e ls fo r packages of rad ioactive m a te r ia ls and p lacard s fo r v e h ic le s ca rry in g rad io activ e m a te r ia l s h a ll conform to the ap p rop ria te m odel in th is P a r t .T he only in s c r ip t io n s w hich s h a ll be m and atory s h a ll be th o se shown in th e se m o d els .

B a s ic t r e f o i l sy m b o l w ith prop ortion s b ased o n a c e n tr a l c i r c l e o f rad ius 4 m m

,20mm r 1* ^mm

Fig-1

3 8

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 53: Regulations for the Safe Transport of Radioactive Materials

PART E 39

F ig . 2

C a te g o ry I -W h ite la b e l

D im e n sio n s g iv e n h e re a re th e a c tu a l' o n es to b e used

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 54: Regulations for the Safe Transport of Radioactive Materials

PART E

F ig . 3

C a te g o ry I I - Y e l lo w la b e l

D im en sio n s g iv e n h e re a re th e a c tu a l o n es to b e used

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 55: Regulations for the Safe Transport of Radioactive Materials

PART E

F ig . 4

C a te g o ry I I I - Y e l lo w la b e l

D im en sio n s g iv e n h e re a re th e a c tu a l o n es to b e used

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 56: Regulations for the Safe Transport of Radioactive Materials

4 2 PART E

F ig . 5

P la c a rd fo r v e h ic le s .

T h e o v e r - a l l sh a p e o f th e p la c a rd m a y b e d ia m o n d , re c ta n g u la r or squ are as in d ic a te d

by th e dashed l in e s . M in im u m d im en sio n s a re g iv e n ; w hen la rg e r d im en sio n s are

used th e r e la t iv e p roportions m ust b e m a in ta in e d .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 57: Regulations for the Safe Transport of Radioactive Materials

A N N E X I

GEN ERAL, DATA

TA BLE I

ACTIVITY-MASS RELATIONSHIP FOR URANIUM AND NATURAL THORIUM

R a d io a c tiv e m a te r ia l c/ g g/ c

U ran iu m

(w t.^ o U 235 p resen t)

0 . 4 5 5 . 0 X 1 0 " 7 2 . 0 X 1 0 6

0 . 72 (n a tu ra l) 7 . 0 6 X 1 0 '7 1 . 4 2 X 1 0 6

1 . 0 7 . 6 X 1 0 -7 1 .3 X 1 0 6

1 . 5 1 . 0 X 1 0 ā€œ6 1 . 0 x i o 6

5 . 0 2 . 7 X i o - 6 3 . 7 X 1 0 s

1 0 . 0 4 . 8 X 1 0 " 6 2 . 1 x i o 5

2 0 . 0 1 . 0 X 1 0 ~ s 1 . 0 X 1 0 5

3 5 . 0 2 . 0 X 1 0 " 5 5 . 0 x i o 4

5 0 . 0 2 . 5 x i o - 5 4 . 0 x i o 4

9 0 . 0 5 . 8 X 1 0 -5 1 . 7 x 104

9 3 . 0 7 . 0 x i o -5 1 . 4 X 10 4

9 5 . 0 9 . 1 X 1 0 - 5 1. 1 X 1 0 4

N a tu ra l th o riu m 1 . 1 1 X i o - ā€™ 9 X 1 0 6 .

4 3

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 58: Regulations for the Safe Transport of Radioactive Materials

4 4 ANNEX I

TA BLE II

CLASSIFICATION OF RADIONUCLIDES INTO GROUPS FO R TRANSPORT PURPOSES

N O T E S : 1. T h e s p e c i f i c a c t i v i t y i s f o r m a t e r i a l c o n s i s t i n g o f o n ly th e l i s t e d n u c l id e .

2 . A n a s t e r i s k i n d i c a t e s th a t t h e r a d i o n u c l i d e h a s b e e n a l l o c a t e d to a g r o u p in a c c o r d a n c e w ith T a b le in A - 3 . 1 . 2 .

S y m b o l R a d io n u c lid e G roupS p e c i f i c a c t iv i ty

(c/ g )

A A rg o n -3 7 (co m p re sse d or

u n co m p ressed )(a )

V I l . o i x i o 5

A rg o n - 4 1 II 4 .2 5 X 107A rg o n -4 1 (u n co m p resse d )(a ) V .

A c A c t in iu m -2 2 7 I 7 .2 X 10A c t in iu m -2 2 8 I 2 .2 4 X 106

A g S i lv e r - 1 0 5 IV 3 .1 1 X 104S i l v e r - l l O m III 4 .7 0 X 103S i lv e r - 1 1 1 IV 1. 57 X 10s

A m A m e r ic iu m -2 4 1 I 3 .2 4A m e r ic iu m -2 4 3 I 1 .8 5 X 10"1

As A r s e n ic -7 3 IV 2 .3 6 X 104A r s e n ic -7 4 IV 1. 01 X 105A r s e n ic -7 6 IV 1. 56 X 106A r s e n ic -7 7 IV 1. 05 X 106

A t A s ta t in e -2 1 1 III 2 . 06 X 106

(a ) Uncompressed shall m ean a t a pressure no: exceeding one atmosphere absolute a t 0Ā°Cand m ean sea-level.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 59: Regulations for the Safe Transport of Radioactive Materials

ANNEX I 4 5

S y m b o l R a d io n u c lid e G roupS p e c i f i c a c t iv i ty

(c/ g )

C f C a l i f o r n iu m -2 4 9 I 3 . 0 5

C a l i f o r n iu m -2 5 0 I 1 . 3 1 X 1 0 2

C a l i fo r n iu m -2 5 2 I 6 . 5 X 1 0 2

C l C h lo r in e -3 6 I I I 3 . 2 1 X 1 0 " 2

C h lo r in e -3 8 IV 1 . 3 3 X 1 0 8

C m C u r iu m -2 4 2 I 3 . 3 2 X 1 0 3

C u r iu m -2 4 3 I 4 . 2 1 X 10

C u r iu m -2 4 4 r 8 . 2 X 10

C u r iu m -2 4 5 i 1 . 0 4 X 1 0 " 1

C u r iu m -2 4 6 i 3 . 6 4 X 1 0 _1

C o C o b a l t - 5 6 * h i 3 . 0 2 X 104

. C o b a l t -5 7 IV - 8 . 5 X 1 0 3

C o b a lt -5 8 m IV 5 . 9 X 1 0 6

C o b a l t -5 8 IV 3 . 13 X 1 0 ā€œ

C o b a l t - 6 0 h i 1. 14 X 1 0 3 ā– 

C r C h ro m iu m -5 1 IV 9 . 2 X 104

C s C a e s iu m -1 3 1 h i 1 X 1 0 5

C a e s iu m -1 3 4 m IV 7 . 4 X 1 0 6

C a e s iu m -1 3 4 h i 1 .2 2 X 1 0 3

C a e s iu m -1 3 5 IV 8 . 8 X 1 0 " 4

C a e s iu m -1 3 6 IV 7 . 4 " X 1 0 4

C a e s iu m -1 3 7 IV 9 , 8 2 X 10

C u C o p p e r -6 4 IV 3 . 8 3 X 1 0 6

D y D y s p r o s iu m -1 5 4 * h i 1 . 5 7 X 1 0 6

D y sp ro siu m -1 6 5 IV 8 . 2 X 1 0 6

D y sp ro siu m -1 6 6 IV 2 . 3 0 X 105

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 60: Regulations for the Safe Transport of Radioactive Materials

4 6 ANNEX I

S y m b o l R a d io n u c lid e G roupS p e c i f i c a c t iv i ty

(c/ g )

Au G o l d - 1 9 3 * III 9 . 3 X 1 0 5

G o l d - 1 9 4 * II I 4 . 1 0 X 1 0 s

G o l d - 1 9 5 * II I 3 . 72 X 1 0 5

G o ld -1 9 6 IV 1 . 2 0 X 1 0 5

G o ld -1 9 8 IV 2 . 4 5 X 1 0 5

G o ld -1 9 9 IV 2 . 0 9 X 1 0 5

Ba B a r iu m -1 3 1 IV 8 . 7 X I O 4

B a r iu m -1 4 0 ' I I I 7 . 3 X I O 4

B e B e r y ll iu m -7 IV 3 . 5 1 X 1 0 s

B i B is m u th -2 0 6 IV 9 . 9 X I O 4

B is m u th -2 0 7 III 2 . 1 6 X 1 0 2

B is m u th -2 1 0 (R a . E) II 1 . 2 4 X 1 0 5

B is m u th -2 1 2 'I I I 1 . 4 7 X 107

Bk B e r k e liu m -2 4 9 I 1 . 8 0 X 10s

Br B r o m in e -8 2 IV 1 . 0 6 X 106

C C a rb o n - 1 4 IV 4 . 5 9

C a C a lc iu m - 4 5 IV 1 . 9 1 X 1 0 4

C a lc iu m - 4 7 IV 5 . 9 X I O 5

Cd C a d m iu m -1 0 9 III 2 . 5 5 X 1 0 3

C a d m iu m -1 1 5 m III 2 . 6 4 X 1 0 4

C a d m iu m -1 1 5 IV 5 . 1 X 10 5

C e ā€¢ C eriu m -1 4 1 IV 2 . 8 0 X 1 0 4

C e r iu m -1 4 3 IV 6 . 6 X I O 5

C e r iu m - 1 4 4 III 3 . 1 8 X 1 0 3

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 61: Regulations for the Safe Transport of Radioactive Materials

ANNEX I 4 7

S y m b o l R a d io n u c lid e G roupS p e c i f i c a c t iv i t y

(c/ g )

Er E r b iu m -1 6 9 IV 8 . 2 X 1 0 4

E r b iu m -1 7 1 IV 2 . 3 5 X 1 0 6

Eu E u r o p iu m -1 5 0 * III 1 . 3 9 X 1 0 6

E u ro p iu m -1 5 2 (A ) ( 9 . 2h ) IV 2 . 2 4 X 1 0 6

E u ro p iu m -1 5 2 (B ) (1 2 . 7 yr) III 1 . 8 5 X 1 0 z

E u ro p iu m -1 5 4 II 1 . 4 5 X 1 0 2

E u ro p iu m -1 5 5 IV 1 . 3 6 X 1 0 3

F F lu o r in e -1 8 IV 9 . 3 X 1 0 7

F e Ir o n -5 5 IV 2 . 2 2 X 1 0 3

I r o n -5 9 IV 4 . 9 2 X 1 0 4

G a G a l l i u m - 6 7 * III 6 . 0 X 105

G a l l iu m - 7 2 IV 3 . 0 9 X 10Ā«

Gd G a d o lin iu m -1 5 3 IV 3 . 6 2 X 1 0 3

G a d o lin iu m -1 5 9 IV 1 . 1 0 X 1 0 s

G e G e r m a n iu m -7 1 IV 1 . 6 1 X 1 0 5

H H y d ro g en -3 - s e e T - T r i t iu m

H f H a fn iu m -1 8 1 IV 1 . 6 2 X 1 0 4

Hg M e rc u r y -1 9 7 m IV 6 . 6 X 1 0 5

M e rc u r y -1 9 7 IV 2 . 4 5 X 1 0 5

M e rc u r y -2 0 3 IV 1 . 3 7 X 1 0 4

H o H o lm iu m -1 6 6 IV 6 . 9 X 1 0 5

I I o d i n e - 1 2 4 * II I 2 . 3 4 X 1 0 5

I o d in e - 12 5 * I I I 1 . 7 4 X 10-1

I o d in e - 1 2 6 III 7 . 8 X 1 0 4

I o d in e - 12 9 II I 1 . 6 2 X 1 0 ' 4

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 62: Regulations for the Safe Transport of Radioactive Materials

4 8 ANNEX I

S y m b o l R a d io n u c lid e G roupS p e c i f i c a c t iv i ty

(c/ g )

I I o d in e - 1 3 1 II I 1 . 2 3 X 1 0 s

I o d i n e - 132 IV 1 . 0 5 X 1 0 7

I o d i n e - 1 3 3 II I 1 . 1 3 X 10Ā«

I o d i n e - 1 3 4 IV 2 . 6 8 X 1 0 7

Io d in e - 1 3 5 IV 3 . 4 8 X 1 0 6

In In d iu m -1 1 3 m IV 1 . 6 0 X 10^

In d iu m -1 1 4 m III 2 . 2 9 X 1 0 4

In d iu m -1 1 5 m IV 6 . 1 X 10Ā«

Ir I r id iu m - 1 9 0 IV 6 . 2 X 1 0 4

Ir id iu m -1 9 2 . III 9 . 1 X 103

I r id iu m - 1 9 4 IV 8 . 5 X 1 0 5

K P o ta s s iu m -4 2 IV 6 . 0 X 1 0 6

P o ta ss iu m - 4 3 * II I 3 . 2 6 X 1 0 s

K r K ry p to n -8 5 m III 8 . 4 X 1 0 6

K ry p to n -8 5 m (u n c o m p r e s s e d )^ V

K ry p to n -8 5 III 3 . 9 7 X 102

K ry p to n -8 5 (u n co m p ressed / 3 ) V I

K ry p to n -8 7 II 2 . 77 X 1 0 7

K ry p to n -8 7 (u n c o m p r e s s e d )^ V

La L a n th a n u m -1 4 0 IV 5 . 6 X 1 0 6

Lu L u t e c iu m - 1 7 2 * III 4 . 5 6 X 1 0 6

L u te c iu m -1 7 7 IV 1 . 0 9 X 1 0 s

M . f . p. M ix e d fiss io n p rod ucts n N ot d e fin ed

M g M a g n e s iu m - 2 8 * i i i 5 . 2 X 1 0 6

Uncompressed shall m ean a t a pressure not exceeding one atmosphere absolute a t 0Ā°Cand m ean sea-level

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 63: Regulations for the Safe Transport of Radioactive Materials

ANNEX I 4 9

S y m b o l R a d io n u c lid e G roupS p e c i f i c a c t iv i t y

(c/ g )

M n M a n g a n e s e -5 2 IV ' 4 . 4 2 X I O 5

M a n g a n e s e -5 4 IV 8 . 3 X I O 3

M a n g a n e s e -5 6 IV 2 . 1 7 X 107

M o M o ly b d e n u m -9 9 IV 4 . 7 3 X 1 0 5

N a S o d iu m -2 2 I I I 6 . 3 X 1 0 3

S o d iu m -2 4 - I V 8 . 7 X 1 0 6

Nb N io b iu m -9 3 m IV 1. 0 5 X 1 0 3

N io b iu m -9 5 IV 3 . 9 3 X 1 0 4

N io b iu m -9 7 ' IV 2 . 6 1 X I O 7

Nd N e o d y m iu m -1 4 7 IV 8 . 0 X 104

N e o d y m iu m -1 4 9 IV 1 . 0 5 X 1 0 7

. N i N i c k e l - 5 6 * III 3 . 6 5 X 1 0 5

N i c k e l - 5 9 IV 8 . 1 X 1 0 ' 2

N ic k e l - 6 3 IV 4 . 5 5 X 10

N ic k e l - 6 5 IV 1 . 8 8 X 1 0 7

Np N e p tu n iu m -2 3 7 I 6 . 9 X 1 0 " 4

N e p tu n iu m -2 3 9 I 2 . 3 3 X I O 5

Os O sm iu m - 1 8 5 . IV 7 . 3 X 1 0 3

O s m iu m -1 9 1 m IV 1 . 1 7 X 105

O s m iu m -1 9 1 IV 4 . 5 6 X 1 0 4

O s m iu m -1 9 3 IV 5 . 3 X I O 5

P P h o sp h o ru s-32 IV 2 . 8 8 X 1 0 s

Pa P r o ta c t in iu m - 2 3 0 I 3 . 2 1 X 1 0 4

P r o ta c t in iu m -2 3 1 I 4 . 5 2 X 1 0 ā€˜ 2

P r o ta c t in iu m -2 3 3 II 2 . 0 8 X 1 0 4

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 64: Regulations for the Safe Transport of Radioactive Materials

5 0 ANNEX I

.S y m b o l R a d io n u c lid e G roupS p e c i f i c a c t iv i ty

(c/ g )

Pb L e a d -2 0 3 IV 2 . 9 7 X 1 0 5

L e a d -2 1 0 II 8 . 8 X 10

L e a d -2 1 2 II 1 . 4 0 X 1 0 '

Pd P a lla d iu m -1 0 3 IV 7 . 5 X 1 0 4

P a lla d iu m -1 0 9 IV 2 . 1 2 X 1 0 6

Pm P r o m e th iu m -1 4 7 IV 9 . 4 X 102

P r o m e th iu m -1 4 9 IV 4 . 2 1 X 1 0 5

Po P o lo n iu m -2 1 0 I 4 . 5 X 1 0 3

Pr P r a s e o d y m iu m -142 IV 1 . 1 5 X 1 0 6

P ra s e o d y m iu m -1 4 3 IV 6 . 6 X 1 0 4

Pt P la t in u m -1 9 1 IV 2 . 2 8 X 1 0 s

P la t in u m -1 9 3 m IV 1 . 9 9 X 1 0 5

P la t in u m -1 9 7 m IV 1 . 2 2 X 1 0 7

P la t in u m -1 9 7 IV 8 . 8 X 105

Pu P lu to n iu m -2 3 8 I 1 . 6 8 X 10

P lu to n iu m -2 3 9 I 6 . 1 7 X 1 0 " z

P lu to n iu m -2 4 0 I 2 . 2 7 X 1 0 ' 1 /

P lu to n iu m -2 4 1 I 1 . 1 4 X 1 0 2

P lu to n iu m -2 4 2 I 3 . 9 0 X 1 0 ā€œ 3

Ra R a d iu m -2 2 3 II 5 . 0 X 1 0 4

R a d iu m -2 2 4 II 1 . 6 0 X 1 0 s

R a d iu m -2 2 6 . I 9 . 8 X 1 0 " 1

R a d iu m -2 2 8 I 2 . 3 4 X 1 0 2

Rb R u b id iu m -8 6 IV 8 . 1 X 1 0 4

R u b id iu m -8 7 IV 6 . 6 X 1 0 ' 8

R u b id iu m n a tu ra l IV 1 . 8 1 X 1 0 - 8

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 65: Regulations for the Safe Transport of Radioactive Materials

ANNEX I 51

S y m b o l R a d io n u c lid e G roupS p e c i f i c a c t iv i t y

(c/ g )

Re R h e n iu m -1 8 3 IV 4 . 6 1 X 103

R h e n iu m -1 8 6 IV 1 . 9 0 X 1 0 s

R h e n iu m -1 8 7 IV 3 . 8 3 X lO - 8

R h e n iu m -1 8 8 IV 1. 0 X 1 0 6

R h en iu m n a tu ra l w 2 . 4 X 1 0 ā€œ8

Rh R h o d iu m -1 0 3 m IV 3 . 2 1 X 1 0 7

R h o d iu m -10 5 IV 8 . 2 X 1 0 5

Rn R a d o n -2 2 0 IV 9 . 4 X 1 0 8

R a d o n -2 2 2 II 1 . 5 4 X 1 0 5

Ru R u th e n iu m -9 7 IV 5 . 5 X 1 0 5

R u th e n iu m -1 0 3 IV 3 . 1 9 X 1 0 4

R u th e n iu m -1 0 5 IV 6 . 6 X 10Ā«

R u th e n iu m -1 0 6 III . 3 . 3 8 X 1 0 3

S S u lp h u r-3 5 IV 4 . 2 9 X 1 0 4

Sb A n tim o n y -1 2 2 IV 3 . 9 0 X 1 0 5

A n tim o n y -1 2 4 III " 1 . 7 6 X 1 0 4

A n tim o n y -1 2 5 III 1 . 4 3 X 1 0 3

S c S c a n d iu m -4 6 III 3 . 3 8 X 1 0 4

S c a n d iu m - 4 7 IV 8 . 2 X 1 0 5

S c a n d iu m -4 8 IV 1 . 4 9 X 10 6

S e S e le n iu m -7 5 IV 1 . 4 4 X 1 0 4

S i S i l i c o n - 3 1 IV ' 3 . 8 6 X 1 0 7

S m S a m a r iu m -1 4 5 * II I 2 . 6 5 X 1 0 3

S a m a r iu m -1 4 7 III 1. 9 5 X 1 0 " 8

S a m a r iu m -1 5 1 IV 2 . 5 5 X 10

S a m a r iu m -1 5 3 IV 4 . 3 5 X 1 0 5

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 66: Regulations for the Safe Transport of Radioactive Materials

5 2 ANNEX I

S y m b o l R a d io n u c lid e G roupS p e c i f i c a c t iv i ty

(c/ g )

Sn T i n - 1 1 3 IV 9 . 7 X I O 3

T i n - 1 1 7 m * III 8 . 0 X 10-*

T i n - 1 2 1 * III 9 . 4 X I O 5

T i n - 1 2 5 IV 1 . 0 5 X 1 0 5

Sr S t r o n t iu m -8 ? m IV 3 . 1 6 X 1 0 7

S tr o n t iu m -8 5 IV 2 . 3 7 X 104

S tr o n t iu m -8 9 III 2 . 88 X 1 0 4

S tro n t iu m -9 0 II 1 . 4 5 X 1 0 2

S tro n t iu m -9 1 III 3 . 5 6 X 1 0 6

S tr o n t iu m -9 2 IV 1 . 2 6 X 1 0 7

T T r it iu m (a s H T O o r H320 ) IV 9 . 7 X 1 0 3

T r it iu m (a s T 2 or H T )

(in fo rm o f co m p resse d or

u n co m p ressed g as) (a ) V II 9 . 7 X 1 0 3

T r i t iu m - a c t iv a t e d lu m in o u s

p a in t or t r it iu m gas

ad sorbed on a so lid c a r r ie r V III 9 . 7 X 1 0 3

T a T a n ta lu m -1 8 2 II I 6 . 2 X 1 0 3

T b T e r b iu m - 1 6 0 I I I 1 . 1 1 X 1 0 4

T c T e c h n e t iu m - 9 6 m IV 3 . 8 1 X 1 0 7

T e c h n e t iu m - 9 6 IV 3 . 2 4 X 1 0 5

T e c h n e t iu m - 9 7 m IV 1 . 4 8 X 1 0 4

T e c h n e t iu m - 9 7 IV 1 .4 2 X 1 0 " 3

T e c h n e t iu m - 9 9 m IV 5 . 2 X 1 0 6

T e c h n e t iu m - 9 9 IV 1 . 7 1 X 1 0 -2

(a ) Uncompressed shall m ean a t a pressure not exceeding one atmosphere absolute a t 0Ā°Cand m ean sea-level

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 67: Regulations for the Safe Transport of Radioactive Materials

ANNEX I 5 3

S y m b o l R a d io n u c lid e G roupS p e c i f i c a c t iv i t y

(c/ g )

T e T e l lu r iu m - 1 2 5 m IV 1 . 8 0 X 1 0 4

T e l lu r iu m - 1 2 7 m IV 9 . 8 X 1 0 3

T e l lu r iu m - 1 2 7 IV 2 . 6 3 X 1 0 6

T e l lu r iu m - 1 2 9m III 2 . 4 7 X 1 0 4

T e l lu r iu m - 12 9 IV 1 . 9 7 X 1 0 7

T e l lu r iu m - 1 3 1 m m 8 . 0 X 1 0 s

T e l l u r i u m - 132 IV 3 . 0 6 X 1 0 s

T h T h o r iu m -2 2 7 i i 3 . 1 7 X 1 0 4

T h o r iu m -2 2 8 i 8 . 3 X 1 0 2

T h o r iu m -2 3 0 i 1 . 9 4 X 1 0 ' 2

T h o r iu m -2 3 1 i 5 . 3 X 1 0 s

T h o r iu m -2 3 2 i n 1 . 1 1 X 1 0 ā€˜ 7

T h o r iu m -2 3 4 i i 2 . 3 2 X 1 0 4

T h o riu m n a tu ra l n i 1 . 1 1 X 1 0 -7

T1 T h a l l iu m - 2 0 0 IV 5 . 8 X 1 0 s

T h a l l iu m - 2 0 1 IV 2 . 1 7 X 1 0 5

T h a l l iu m - 2 0 2 IV 5 . 4 X 1 0 4

T h a l l iu m - 2 0 4 III 4 . 2 8 X 1 0 2

T m T h u l iu m - 1 6 8 * I I I 8 . 9 X 1 0 3

T h u liu m -1 7 0 III 6 . 0 X 1 0 3

T h u l iu m - 1 7 1 IV 1 . 1 2 X 1 0 3

U U ra n iu m -2 3 0 II 2 . 7 3 X 1 0 4

U ra n iu m -2 3 2 I 2 . 0 8 X 10

U ra n iu m -2 3 3 I I 9 . 5 X 1 0 ā€˜ 3

U ra n iu m -2 3 4 II 6 . 2 X 1 0 - 3

U ra n iu m -2 3 5 II I 2 . 1 4 X 1 0 " 6

U ra n iu m -2 3 6 II 6 . 3 X 1 0 - 5

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 68: Regulations for the Safe Transport of Radioactive Materials

5 4 ANNEX I

S y m b o l R a d io n u c lid e G roupS p e c i f i c a c t iv i t y

(c/ g )

U U ra n iu m -2 3 8 III 3 . 3 3 X 1 0 ā€˜ 7

U ra n iu m n a tu ra l III 7 . 0 6 X lO " 7

V V a n a d iu m - 4 8 IV 1 . 7 0 X 1 0 5

V a n a d iu m - 4 9 * III 8 . 1 X 1 0 3

W T u n g s te n -1 8 1 IV 4 . 9 8 X 1 0 3

T u n g s te n -1 8 5 IV 9 . 7 X 1 0 3

T u n g s te n - 1 8 7 IV 7 . 0 X 1 0 5

X e X e n o n - 1 2 5 * (co m p re sse d or

u n co m p ressed ) (a ) III 1 . 3 9 X 1 0 6

X e n o n - 1 3 1 m II I 8 . 3 X 1 0 4

X e n o n - 1 3 1 m (u n co m p resse d )(a ) V

X e n o n - 1 3 3 III 1 . 8 6 X 1 0 5

X e n o n - 1 3 3 (u n co m p ressed ) ( a ) V I

. X e n o n - 1 3 5 II 2 . 5 4 X 1 0 6

X e n o n - 1 3 5 (u n co m p ressed ) (a ) V

Y Y t t r i u m - 8 8 * II I 1 . 4 3 X 1 0 4

Y t t r iu m -9 0 IV 5 . 3 X 1 0 5

Y t t r iu m -9 1 m III 4 . 1 1 X 1 0 7

Y t t r iu m - 9 1 I I I 2 . 5 0 X 104

Y t t r iu m -9 2 IV 9 . 5 X 1 0 6

Y t t r iu m - 9 3 IV : 3 . 2 4 X 1 0 6

Y b Y t te r b iu m - 1 7 5 IV 1 . 78 X 1 0 s

Z n Z i n c - 6 5 IV 8 . 2 X 1 0 3

Z in c - 6 9 m IV 3 . 2 9 X 1 0 6

Z i n c - 6 9 IV 5 . 3 X 1 0 7

Z r Z ir c o n iu m -9 3 IV 3 . 5 0 X 1 0 - 3

Z ir c o n iu m -9 5 II I 2 . 1 2 X 1 0 4

Z ir c o n iu m -9 7 IV 1 . 9 0 X 1 0 6

(a ) Uncompressed shall m ean a t a pressure not exceeding one atmosphere absolute a t 6Ā°Cand m ean sea-level.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 69: Regulations for the Safe Transport of Radioactive Materials

ANNEX I 5 5

TA BLE III

N E U T R O N F L U X T O B E R E G A R D E D AS E Q U IV A L E N T T O A D O SE R A T E O F 1 m r/ h

En erg y o f n eu tro nF lu x e q u iv a le n t to 1 m r/h

( n / c m 2- s)

T h e r m a l 2 6 8

5 k eV 2 2 8

2 0 keV 112

1 0 0 k eV 3 2

5 0 0 k eV 12

1 M eV 7 . 2

5 M eV 7 . 2

10 M eV 6 . 8

N o te : F lu x e q u iv a le n t fo r e n e r g ie s b e tw e e n th o se l is te d a b o v e should b e o b ta in e d by

in te rp o la t io n .

TA BLE IV

M A X IM U M P E R M IS S IB L E L E V E L S O F R A D IO A C T IV E C O N TA M IN A TIO N

C o n ta m in a n tM a x im u m p e rm is s ib le le v e l

O ic/ cm 2 )

B e ta or g a m m a e m itte r s

A lp h a e m it te r s

i o - 4

i o - 5

N o te : T h e a b o v e le v e ls a r e p e rm is s ib le w hen a v e ra g e d o v er a n y a re a o f 3 0 0 c m 2 0 f a n y p a r t

o f th e s u rfa c e .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 70: Regulations for the Safe Transport of Radioactive Materials

5 6 ANNEX I

TABLE V

EXPLANATION OF T A BL E S

1 . T a b le s VA to VC have been p rep ared to fa c ili ta te the d e te rm iĀ­nation of m inim um seg reg a tio n d is ta n ce s sep a ra tin g p ack ag es con Ā­ta in in g ra d io a c tiv e m a te r ia ls fro m p e rs o n s and undeveloped f i lm .

2. In using th e se T a b le s , i t is n e c e s s a ry to evaluate the tim e during which the g e n era l public and tran sp ort w orkers a re exposed to rad ioĀ­a c tiv e p ack ag es o v e r a p eriod of a y e a r . A p e r m is s ib le d o s e -r a te of exp o su re can then be obtained by dividing the annual p e rm is s ib le dose fo r the ca teg o ry of p erson s concerned by the annual tim e of e x Ā­p o su re . In the T a b le s , a colum n corresp ond ing to that d o s e -ra te can th en be s e le c te d w hich would in d ica te th e re le v a n t s e g re g a tio n d is ta n c e s .

3 . F o r convenience T a b le VD h as been included to provide fo r the co n v ersio n fro m dose to dose ra te ,

annual p e rm is s ib le dose ,,e .g . --------- ā€”f----------- ---------------- = m r/hannual hours of exposure

4 . In addition, consid eration m ust be given to the p ossib le exposure of film in storag e o r during a sp ecific tr ip . The T ab les should thenbe applied to ensure that the dose to film does not exceed 10 m r.

5. T ab le VA show s, fo r varying num bers of packages and c o r r e s Ā­ponding tra n sp o rt in d ex es , the m inim um d is ta n ce s a t which an e x Ā­

p o s u r e dose of 10 m r w ill be rece iv ed when the exposure period has the value s ta te . The T ab le m ay thus be used fo r the seg reg a tio n of packages containing rad ioactive m a te ria l from undeveloped film when th e re i s no in terven in g shielding by w alls , n o n -rad io activ e consignĀ­m ents o r o th er n o n -rad io activ e m a te r ia ls .

6 . T a b le V B show s, fo r varying num bers of packages and c o r r e s Ā­ponding tra n sp o rt in d ex es, the m inim um d is ta n ce s at w hich an e x Ā­posure dose of 100 m r w ill be received when the exposure period has the value s ta te d . T h is T a b le m ay be used to d eriv e the seg reg a tio n d istan ces betw een packages containing rad ioactive m ateria ls , and p e rĀ­son s, when th e re is no in terven in g sh ield ing by w alls, n o n -rad io activ e con sig n m en ts o r o th er n o n -rad io activ e m a te r ia ls .

7. A lte rn a tiv e ly , the T a b le m ay be used to d eterm in e d ir e c t ly the seg reg a tio n d is ta n ce s betw een p ackag es containing rad io activ e m aĀ­te r ia ls , and undeveloped film when th e re is su ffic ie n t in te rv e n in g sh ield in g to re d u ce the exp o su re d ose ra te by a fa c to r of 10 .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 71: Regulations for the Safe Transport of Radioactive Materials

TABLE V A

D IS T A N C E S F R O M T H E S U R F A C E O F P A C K A G E S W IT H NO IN T E R V E N IN G S H IE L D IN G M A T E R IA L AND F O R A T O T A L R A D IA T IO N E X P O S U R E . O F 10 m r O R E Q U IV A L E N T

Category of package

Number of pa cka ge

Number o f

2 3 4 5 8

Exposure t im e in hours (days)

10 12 15 20 24

(1)

48( 2 ) ā€¢

72(3)

120(5)

24 0 ā€˜ (10)

360(1 5)

480(20)

720(30 )

960(40)

1200(5 0 )

2000(8 0)

transportindexes

Minimum distance from surface in metres

I Not applicable

1 + 0 . 3 0 . 4 0 . 5 0 . 5 0 . 6 0 . 7 0 . 8 0 . 9 1 . 0 1 . 1 . 1 . 6 1 . 9 2 . 4 3 . 5 4 . 3 4 . 9 6 . 0 6 . 9 7 . 8 1 0 . 02 1 + 0 . 4 0 . 5 0 . 6 0 . 7 0 . 9 1 . 0 1 . 1 1 . 2 1 . 4 1 . 5 2 . 2 2 . 7 3 . 5 4 . 9 6 . 0 6 . 9 8 . 5 1 0 . 0 1 1 . 0 1 4 . 0

3 + 0 . 5 0 . 6 0 . 7 0 . 8 1 .1 1 . 2 1 . 3 1 . 5 1 . 7 1 . 9 2 . 7 3 . 3 4 . 2 6 . 0 7 . 4 8 . 5 1 0 . 0 1 2 . 0 1 3 . 0 1 7 . 0

4 2 0 . 3 0 . 6 0 . 7 0 . 8 1 . 0 1 . 2 1 . 4 1 . 5 1 . 7 2 . 0 2 . 2 3 . 2 3 . 8 4 . 9 6 . 9 8 . 5 1 0 . 0 1 2 . 0 1 4 . 0 1 6 . 0 2 0 . 0

5 0 . 4 0 . 6 0 . 8 0 . 9 1 . 1 1 . 4 1 . 6 1 . 7 1 : 9 2 . 2 2 . 4 3 . 5 4 . 3 5 . 5 7 . 7 1 0 . 0 1 1 . 0 1 4 . 0 1 6 . 0 1 8 . 0 . 2 3 . 0

6 3 0 . 4 0 . 7 0 . 9 1 . 0 1 . 2 1 . 5 1 . 7 1 . 9 2 . 1 2 . 4 2 . 6 3 . 8 4 . 8 6 . 0 9 . 3 1 1 . 0 1 2 . 0 1 5 . 0 1 7 . 0 * 1 9 . 0 2 5 . 0 '

8 4 0 . 5 0 . 8 1 . 0 1 . 1 1 . 4 1 . 7 1 . 9 2 . 2 2 . 4 2 . 8 3 . 1 4 . 3 5 . 5 6 . 9 1 0 . 0 1 2 . 0 1 4 . 0 1 7 . 0 2 0 . 0 2 2 . 0 2 8 . 0

II 10 5 0 . 5 0 . 8 1 . 1 1 . 3 1 . 5 1 . 9 2 . 2 2 . 4 2 . 8 3 . 2 3 . 5 4 . 9 6 . 0 7 . 8 1 1 . 0 1 3 . 0 1 6 . 0 1 9 . 0 * 2 2 . 0 2 5 . 0 3 2 . 0

15 0 . 6 1 . 0 1 . 3 1 . 5 1 . 9 2 . 3 2 . 7 2 . 9 3 . 3 3 . 9 4 . 2 6 . 0 6 . 9 9 . 5 1 3 . 0 1 6 . 0 1 9 . 0 2 3 . 0 2 7 . 0 3 1 . 0 * 3 9 . 020 10 0 . 7 1 .2 . 1 . 5 1 . 7 . 2 . 2 2 . 6 3 . 2 3 . 4 3 . 9 4 . 5 4 . 9 6 . 9 8 . 5 1 1 . 0 1 6 . 0 1 9 . 0 2 2 . 0 2 7 . 0 3 1 . 0 3 5 . 0 4 5 . 0

25 0 . 8 1 . 3 1.7. 2 . 0 2 . 4 3 . 0 3 . 5 3 . 8 4 . 3 4 . 9 5 . 5 7 . 7 1 0 . 0 1 2 . 0 1 8 . 0 2 1 . 0 2 5 . 0 3 0 . 0 3 5 . 0 3 9 . 0 5 0 . 0

30 15 0 . 8 1 . 4 1 . 9 2 . 2 2 . 6 3 . 2 3 . 8 4 . 2 4 . 7 5 . 3 6 . 0 8 . 3 1 1 . 0 1 3 . 0 2 0 . 0 2 3 . 0 2 7 . 0 3 3 . 0 3 8 . 0 * 4 3 . 0 5 5 . 0

35 0 . 9 1 . 5 2 . 1 2 . 3 2 . 8 . 3 . 5 4 . 1 4 . 6 5 . 3 5 . 7 6 . 5 9 . 3 1 2 . 0 1 4 . 0 2 1 . 0 2 5 . 0 2 9 . 0 3 6 . 0 4 2 . 0 * 4 6 . 0 6 0 . 0

40 20 1 . 0 1 . 6 2 . 2 2 . 4 3 . 0 3 . 7 4 . 3 4 . 9 5/5 6 . 1 6 . 8 1 0 . 0 1 2 . 0 1 5 . 0 2 2 . 0 2 7 . 0 3 1 . 0 3 8 . 0 4 5 . 0 5 0 . 0 6 5 . 0

50 25 1 . 1 1 . 9 ' 2 . 4 2 . 8 3 . 4 4 . 2 4 . 7 5 . 3 6 . 0 6 . 7 7 . 5 1 1 . 0 1 3 . 0 1 7 . 0 2 5 . 0 2 9 . 0 * 3 4 . 0 * 4 2 . 0 * 5 0 . 0 5 5 . 0 7 0 . 0

60 30 1 . 2 2 . 1 2 . 6 3 . 2 3 . 7 4 . 7 6 . 3 6 . 0 6.'7 7 . 5 8 . 7 1 2 . 0 1 5 . 0 1 9 . 0 2 7 . 0 3 2 . 0 3 8 . 0 4 6 . 0 5 5 . 0 6 0 . 0 7 5 . 0

80 40 1 . 4 2 . 4 3 . 1 3 . 5 4 . 0 5 . 3 6 . 0 6 . 7 7/5 8 . 5 1 0 . 0 1 4 . 0 1 7 . 0 2 2 . 0 3 1 . 0 3 8 . 0 4 5 . 0 5 5 . 0 6 5 . 0 7 0 . 0 8 5 . 0

100 50 1 . 6 2 . 7 3 . 5 3 . 8 4 . 4 5 . 9 6 . 6 7 . 3 8 J3 9 . 5 1 1 . 0 1 5 . 0 1 9 . 0 2 5 . 0 3 5 . 0 4 2 . 0 5 0 . 0 6 0 . O' 7 0 . 0 8 0 . 0 9 5 . 0

2 0 . 5 0 . 6 0 . 8 0 . 9 1 . 0 1 . 2 1 . 4 1 . 5 1 . 7 2 . 0 2 . 2 3 . 1 3 . 8 4 . 9 6 . 9 8 . 5 1 0 . 0 1 2 . 0 1 4 . 0 1 6 . 0 2 0 . 05 0 . 7 1 . 0 1 . 2 ā€¢ 1 . 4 1 . 6 2 . 0 2 . 2 2 . 4 2 . 8 3 . 2 3 . 5 4 . 9 6 . 0 7 . 7 ' 1 1 . 0 1 4 . 0 1 6 . 0 1 9 . 0 2 2 . 0 2 5 . 0 3 2 . 0

10 1 . 0 1 . 4 . 1 . 7 2 . 0 2 . 2 2 . 8 3 . 2 3. 5 3 . 9 4 . 5 4 . 9 6 . 9 8 . 5 1 1 . 0 1 6 . 0 1 9 . 0 2 2 . 0 2 7 . 0 3 1 . 0 3 5 . 0 4 5 . 02 20 1 . 4 2 . 0 2 . 4 2 . 8 3 . 2 4 . 0 4 . 5 4 . 9 5 . 5 6 . 3 6 . 9 1 0 . 0 1 2 . 0 1 5 . 0 2 2 . 0 2 7 . 0 3 1 . 0 3 8 . 0 4 5 . 0 5 0 . 0 6 5 . 03 30 1 . 7 2 . 4 3 . 0 3 . 5 3 . 9 4 . 9 5 . 5 6 . 0 6 . 7 7 . 7 8 . 5 1 2 . 0 1 5 . 0 1 9 . 0 2 7 . 0 3 3 . 0 3 8 . 0 4 5 . 0 5 5 . 0 6 0 . 0 7 5 . 04 40 2 . 0 2 . 8 3 . 5 4 . 0 4 . 5 5 . 7 6 . 3 6 . 9 7 . 7 8 . 9 1 0 . 0 1 5 . 0 1 7 . 0 2 2 . 0 3 1 . 0 3 8 . 0 4 5 . 0 5 5 . 0 6 5 . 0 7 0 . 0 8 5 . 0

5 50 2 . 2 3 . 2 3 . 9 4 . 5 5 . 0 6 . 3 7 . 0 7 . 7 8 . 7 1 0 . 0 1 1 . 0 1 6 . 0 1 9 . 0 2 5 . 0 3 5 . 0 4 5 . 0 5 0 . 0 6 0 . 0 7 0 . 0 8 0 . 0 9 5 . 0

6 60 2 . 4 3 . 5 4 . 3 5 . 0 5 . 5 6 . 9 7 . 7 , 9 . 3 1 0 .0 1 1 . 0 1 2 . 0 1 7 . 0 2 1 . 0 2 7 . 0 3 8 . 0 4 8 . 0 5 5 . 0 6 5 . 0 * 7 5 . 0 8 5 . 0 -

III 8 80 2 . 8 4 . 0 5 . 0 5 . 7 6 . 3 8 . 0 8 . 9 10,0. 1 1 . 0 1 3 . 0 1 4 . 0 2 0 . 0 2 4 . 0 3 1 . 0 4 5 . 0 5 5 . 0 * 6 0 . 0 7 5 . 0 9 0 . 0 9 5 . 0 -

10 100 3 . 2 4 . 5 5 . 6 6 . 3 7 . 0 8 . 9 1 0 . 0 li.o 1 2 .0 1 4 . 0 1 6 . 0 2 2 . 0 2 7 . 0 3 5 . 0 5 0 . 0 6 0 . 0 ' 7 0 . 0 8 5 . 0 1 0 0 . 0 -

15 150 3 . 9 5 . 5 6 . 7 7 . 7 8 . 9 1 1 . 0 1 2 . 0 1 3 . 0 1 5 . 0 1 7 . 0 1 9 . 0 2 2 . 0 3 3 . 0 4 2 . 0 6 0 . 0 7 5 . 0 8 5 . 0 -20 200 4 . 5 6 . 3 7 . 7 8.9/ 1 0 . 0 1 3 . 0 1 4 . 0 1 6 . 0 1 7 . 0 2 0 . 0 2 2 . 0 3 1 . 0 3 8 . 0 5 0 . 0 7 0 . 0 8 5 . 0 * 9 5 . 0 - -25 250 4 . 9 7 . 0 8 . 7 1 0 . 0 1 1 . 0 1 4 . 0 1 6 . 0 1 7 . 0 1 9 .0 2 3 . 0 2 5 . 0 3 5 . 0 4 2 . 0 5 5 . 0 8 0 . 0 * 9 5 . 0 - - -30 300 5 . 3 7 . 7 1 0 . 0 1 1 . 0 1 2 . 0 1 5 . 0 1 7 . 0 1 9 . 0 2 2 .0 2 5 . 0 2 7 . 0 3 8 . 0 4 7 . 0 6 0 . 0 8 5 . 0 - - - -35 350 5 . 7 8 . 3 1 1 . 0 1 2 . 0 1 3 . 0 1 7 . 0 1 9 . 0 2 1 . 0 2 4 .0 2 7 . 0 2 9 . 0 4 2 . 0 5 1 . 0 6 5 . 0 9 0 . 0 - - - -40 4 00 6 . 1 8 . 9 1 1 . 0 1 3 . 0 1 4 . 0 1 8 . 0 2 0 . 0 2 2 . 0 2 5 .0 2 8 . 0 3 1 . 0 4 5 . 0 5 5 . 0 7 0 . 0 1 0 0 . 0 ā€¢ - - - -50 500 6 . 7 1 0 . 0 1 2 . 0 1 4 . 0 1 6 . 0 2 0 . 0 22 . 0 2 4 . 0 2 8 . 0 3 2 . 0 3 5 . 0 5 0 . 0 6 0 . 0 7 5 . 0 ā€¢ ' ā–  ā–  ' ā–  "

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 72: Regulations for the Safe Transport of Radioactive Materials

TABLE VB

D IS T A N C E S F R O M T H E S U R F A C E O F P A C K A G E S W IT H NO IN T E R V E N IN G SH IE L D IN G M A T E R IA L F O R A T O T A L R A D IA T IO N E X P O S U R E O F 1 0 0 m r , O R W H E R E S U F F IC IE N T S H IE L D IN G M A T E R IA L IS P R E S E N T T O R E D U C E T H E R A D IA T IO N B Y A F A C T O R O F 10 ,

F O R A T O T A L R A D IA T IO N E X P O S U R E O F 10 m r

Category o f package.

Number of package

1 2 3 4 5 8 10

Exposure t im e in hours (days)

12 15 20 24

(1)

48(2) ā– 

72(3)

120(5)

240(10)

360(15)

480(2 0)

720(3 0)

960(4 0)

1200(50)

2000(8 0 )

Number of transport indexes

Mini mu m distance from surface in metres

j Not app licable

1 + + + + + + + + + 0 . 3 0 . 4 0 . 5 0 . 6 0 . 8 1 . 1 1 . 3 1 . 6 1 . 9 2 . 2 2 . 4 3 . 2

2 1 + + + + + + + + 0 . 3 0 . 4 0 . 5 0 . 7 0 . 8 1 . 1 1 . 5 1 . 9 2 . 2 2 . 7 3 . 1 3 . 5 4 . 5

3 + + + + + + + 0 . 3 0 . 4 0 . 5 0 . 6 0 . 8 1 . 0 1 . 3 1 . 9 2 . 3 2 . 7 3 . 3 3 . 8 4 . 2 5 . 5

4 2 + + + + + + - 0 . 3 0 . 4 0 . 5 0 . 6 0 . 6 0 . 9 1 . 2 1 . 5 2 . 2 2 . 7 3 . 2 3 . 8 4 . 4 4 . 9 6 . 3

5 + + + + + +ā€¢ 0 . 4 0 . 4 0 . 5 0 . 6 0 . 7 1 . 0 1 . 3 1 . 7 2 . 4 3 . 0 3 . 5 4 . 3 - 4 . 9 5 . 5 7 . 0

6. 3 + + + + + 0 . 3 0 . 4 0 . 5 0 . 5 0 . 7 o ; 8 1 . 1 1 . 4 1 . 9 2 . 6 3 . 2 3 . 8 4 . 8 5 . 5 6 . 0 7 . 7

8 4 + + + + + 0 . 4 0 . 5 0 . 5 ā€¢ 0 . 6 0 . 8 0 . 9 1 . 3 1 . 6 2 . 2 3 . 1 3 . 7 4 . 3 5 . 5 6 . 0 6 . 9 8 . 9

II 10 5 + + + + + 0 . 4 0 . 5 0 . 6 ā€™ 0 . 7 0 . 8 1 . 0 1 . 5 1 . 8 2 . 4 3 . 5 4 . 2 4 . 9 6 . 0 7 . 1 7 . 8 10. .0

15 + + + + + 0 . 5 . 0 . 6 0 . 7 0 . 8 1 . 0 1 . 2 1 . 8 2 . 2 2 . 9 4 . 2 4 . 9 6 . 0 7 . 4 8 . 3 9 . 5 1 2 . 0

20 10 + + + + 0 . 3 0 . 5 0 . 7 0 . 8 0 . 9 1 . 2 1 . 3 2 . 0 2 . 5 3 . 4 4 . 9 5 . 9 6. .9 8 . 5 1 0 . 0 1 1 . 0 1 4 . 0

25 + + + Ā„ 0 . 4 0 . 6 0 . 8 0 . 9 1 . 1 1 . 3 . 1 . 5 2 . 3 2 . 8 3 . 8 5 . 5 ' 6 . 6 7 . 7 1 0 . 0 11.0 1 2 . 0 1 6 . 0

30 15 + + + + 0 . 4 0 . 7 0 . 8 1 . 0 1 . 2 1 . 4 1 . 7 2 . 5 3 . 1 4 . 2 6 . 0 7 . 2 8 . 3 11.0 1 2 . 0 1 3 . 0 1 8 . 0

35 + + + 0 . 3 0 . 5 0 . 8 0 . 9 1 . 1 1 . 3 1 . 5 1 . 8 2 . 7 3 . 4 4 . 6 6 . 3 7 . 7 9 . 3 1 2 . 0 * 1 3 . 0 1 4 . 0 . 1 9 . 0

40 ā€™20 + + + 0 . 3 ' 0 . 5 ' 0 . 8 0 . 9 1 . 1 1 . 3 1 . 6 1 . 9 . 2 . 8 . 3 . 6 4 . 9 6 . 8 8 . 5 1 0 . 0 12. 0 1 3 . 0 1 5 . 0 2 0 . 0

50 25 + + + 0 . 4 0 . 5 - 0 . 9 - 1 . 1 1 . 3 1 . 5 1 . 9 2 . 1 3 . 2 4 . 0 5 . 3 7 . 5 9 . 3 11.0 13. 0 1 5 . 0 1 7 . 0 * 2 2 . 0

60 30 + + + 0 . 4 0 . 6 1 . 0 1 . 2 1 . 4 1 . 7 2 . 1 2 . 4 3 . 6 4 . 6 5 . 9 8 . 5 1 0 . 0 1 2 . 0 1 5 . 0 1 7 . 0 2 0 . 0 2 5 . 0

80 40 + + + 0 . 5 0 . 7 1 . 1 1 . 3 1 . 6 2. 0 2 . 4 2 . 7 4 . 0 5 . 2 6 . 5 1 0 . 0 1 2 . 0 1 4 . 0 1 7 . 0 2 0 . 0 2 2 . 0 2 8 . 0

100 50 + 0 . 3 0 . 5 0 . 7 1 . 3 1 . 5 1 . 8 2 . 2 2 . 6 3 . 0 4 . 4 5 . 7 7 . 1 11.0 1 3 . 0 1 5 . 0 1 9 . 0 2 2 . 0 2 5 . 0 3 2 . 0

2 + + + + 0 . 3 0 . 4 0 . 5 0 . 5 0 . 6 0 . 6 0 . 8 1 . 0 1 . 2 1 . 5 2 . 2 2 . 7 3 . 1 3 . 8 4 . 4 4 . 9 6 . 3. 5 + 0 . 3 0 . 4 0 . 5 0 . 5 0 . 6 0 . 7 0 . 8 0 . 9 1 . 0 1 . 1 1 . 5 1 . 9 2 . 5 3 . 5 4 . 2 4 . 9 6 . 0 6 . 9 7 . 7 1 0 . 0

1 10 0 . 3 0 . 4 0 . 5 0 . 6 0 . 7 0 . 9 1 . 0 1 . 1 1 . 2 1 . 4 ā€¢ 1 . 6 2 . 2 2 . 7 3 . 5 4 . 9 6 . 0 6 . 9 8 . 5 1 0 . 0 11.0 1 4 . 0

2 20 0 . 4 0 . 6 0 . 7 0 . 8 1 . 0 1 . 2 1 . 4 1 . 5 1 . 7 2 . 0 2 . 2 3 . 2 4 . 0 4 . 9 6 . 9 8 . 5 1 0 . 0 1 2 . 0 - 1 4 . 0 1 6 . 0 1 9 . 0

3 30 0 . 5 0 . 7 0 . 9 1 . 1 1 . 2 1 . 5 1 . 7 1 . 9 2 . 1 2 . 4 2 . 7 3 . 9 4 . 9 6 . 0 8 . 5 1 0 . 0 1 2 . 0 1 5 . 0 1 7 . 0 1 9 . 0 2 3 . 0

4 40 0 . 6 0 . 8 1 . 0 1 . 2 1 . 4 1 . 7 2 . 0 2 . 2 ' 2 . 4 2 . 8 3 . 2 4 . 5 5 . 5 6 . 9 1 0 . 0 1 2 . 0 1 4 . 0 1 7 . 0 ā– 20.0 2 2 . 0 2 7 . 0

5 50 0 . 6 0 . 9 1 . 1 1 . 4 1 . 6 1 . 9 2 . 2 2 . 4 2 . 7 3 . 2 3 . 5 5 . 0 6 . 0 7 . 7 11.0 1 4 . 0 1 6 . 0 1 9 . 0 2 3 . 0 2 5 . 0 3 2 . 0

6 60 0 . 7 1 . 0 1 . 2 1 . 5 1 . 7 2 . 1 2 . 4 2 . 6 3 . 0 3 . 5 3 . 8 5 . 3 6 . 5 9 . 3 1 2 . 0 1 5 . 0 1 7 . 0 2 1 . 0 2 5 . 0 2 7 . 0 3 5 . 0

8 80 0 . 8 1 . 1 1 . 5 1 . 7 1 . 9 . 2 . 4 2 . 8 3 . 1 3 . 5 4 . 0 4 . 3 6 . 0 7 . 5 1 0 . 0 1 4 . 0 1 7 . 0 2 0 . 0 2 4 . 0 2 8 . 0 3 1 . 0 4 0 . 0

III 10 100 0 . 8 ā€¢1.3 1 . 6 1 . 9 ā€¢ 2 . 2 . 2 . 8 3 . 2 3 . 5 4 . 0 4 . 5 4 . 9 6 . 9 8 . 5 11.0 1 6 . 0 * 1 9 . 0 2 2 . 0 2 7 . 0 3 2 . 0 3 5 . 0 4 5 . 0

15 150 1 . 0 1 . 5 1 . 9 2 . 3 2 . 7 3 . 3 3 . 9 4 . 2 4 . 9 5 . 5 6 . 0 8 . 5 1 0 . 0 1 3 . 0 1 9 . 0 2 2 . 0 2 7 . 0 3 3 . 0 3 8 . 0 4 2 . 0 5 5 . 0

20 200 1 . 2 1 . 7 2 . 4 2 . 6 . 3 . 2 3 . 9 4 . 5 4 . 9 5 . 5 6 . 3 6 . 9 1 0 . 0 1 2 . 0 1 6 . 0 2 2 . 0 2 7 . 0 3 1 . 0 3 8 . 0 4 2 . 0 5 0 . 0 6 5 . 0

25 250 1 . 3 2 . 0 2 . 6 2 . 9 ā€™ 3 . 5 4 . 3 4 . 9 5 . 5 6 . 3 7 . 0 7 . 7 1 1 . 0 ' 1 4 . 0 1 8 . 0 2 5 . 0 3 0 . 0 3 5 . 0 4 2 . 0 5 0 . 0 5 5 . 0 7 0 . 0

30 300 1 . 4 2 . 2 2 . 8 3 . 3 3 . 8 4 . 7 5 . 3 6 . 0 6 . 9 7 . 7 8 . 3 1 2 . 0 1 5 . 0 2 0 . 0 2 7 . 0 3 3 . 0 3 8 . 0 4 7 . 0 5 5 . 0 6 0 . 0 8 0 . 0

35 35 0 1 . 5 2 . 3 3 . 0 3 . 5 4 . 1 5 . 1 5 . 7 6 . 3 7 . 5 8 . 3 9 . 3 1 3 . 0 1 6 . 0 2 1 . 0 2 9 . 0 3 6 . 0 4 2 . 0 5 1 . 0 6 0 . 0 6 5 . 0 8 5 . 0

40 - 400 1 . 6 2 . 4 3 . 2 3 . 7 4 . 3 5 . 5 6 . 1 6 . 8 7 . 8 8 . 9 1 0 . 0 1 4 . 0 1 7 . 0 2 2 . 0 3 1 . 0 3 8 . 0 4 5 . 0 5 5 . 0 6 5 . 0 7 0 . 0 9 0 . 0

50 50 0 1 . 9 2 . 8 3 . 6 4 . 2 4. 7 6 . 0 6 . 7 7 . 5 8 . 9 1 0 . 0 11.0 1 6 . 0 1 9 . 0 2 5 . 0 3 5 . 0 4 5 . 0 5 0 . 0 6 0 . 0 7 0 . 0 8 0 . 0 1 0 0 ; 0

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 73: Regulations for the Safe Transport of Radioactive Materials

TABLE VC

D IS T A N C E S F K O M T H E S U R F A C E O F P A C K A G E S W IT H N O IN T E R V E N IN G S H IE L D IN G M A T E R IA L AND F O R A T O T A L R A D IA T IO N D O S E O F 1 0 0 0 m r ,O R W IT H S U F F IC IE N T IN T E R V E N IN G SH IE L D IN G M A T E R IA L T O R E D U C E T H E R A D IA T IO N B Y A F A C T O R O F 10 F O R A T O T A L R A D IA T IO N D O S E O F 1 0 0 m r ,

O R W H E R E T H E R E IS S U F F IC IE N T S H IE L D IN G M A T E R IA L T O R E D U C E T H E R A D IA T IO N B Y A F A C T O R O F 1 0 0 ,. F O R 'A T O T A L R A D IA T IO N D O S E O F 1 0 m r

Exposure t i m e in hours (days) ā€¢ .

1 2 3 4 5 8 ā€™ 10 12 ā€¢ 15 ' 20 24 48 72 1 20 2 40 36 0 4 80 7 20 960 12 0 0 2000

1------------------ā€” ------------------------------------ ----------------------------------_-------------------------------------_ _ f C1 ) ( 2 ) ( 3 ) ā€˜ ( 5 ) <1 0 > <1 5 > <2 0 > <3 0 > <4 0 > <5 Ā° ) <8 0 >

Category o f Number o f Number o f ' ā€œ ---------------------------------------------package p ack ag e transport

indexes

Minimum distance from surface in metres

I ā€™ Not appl icab le

1 . +r .-- _ __ . +_. _ + _ + + - + + + + 0 . 4 0 . 4 0 . 5 0 . 6 0 . 7 . 0 . 8 1 . 0

2 1 + + + + ' + + + + + + + + + + ' 0 . 6 T!1~ ~ ' O'. 8 " " 1 . 0 j i . r ' - : 1 . 4

3 + + + + + + + + + + + + + 0 . 3 0 . 6 0 . 7 0 . 8 1 . 0 1 . 2 1 . 3 1 . 7

4 - 2 + + + + + + + + + + + + + 0 . 4 0 . 7 0 . 8 0 . 9 1 . 2 1 . 4 1 . 5 2 . 0

5 + + + + + + + + + + + + + 0 . 4 0 . 8 ā–  0 . 9 1 . 0 1 . 3 1 . 6 1 . 7 2 . 2

6 3 -+ ā€¢ā€™ + + + + + + + + + + + 0 . 3 0 . 5 0 . 9 1 . 0 1 . 2 1 . 4 1 . 7 1 . 9 2 . 4

8 4 + + + + + + + + + + + + 0 . 4 0 . 5 1 . 0 ' 1 . 2 1 . 4 1 . 6 1 . 9 2 . 1 2 . 8

-1 0 . 5 . .Ā« .+ ā€ž + + + + + + + + + + + 0 . 4 0 . 6 1 . 1 1 . 3 1 . 6 1 . 8 2 . 1 2 . 4 3 . 2

15 + + + + + + + + + + + + 0 . 5 ' " 0 . 7 1 . 3 1 . 6 1 . 8 2 . 2 2 . 6 2 . 9 3 . 9

20 10 + + + + + + + + + ' + + 0 . 3 0. .5 0..8; 1 . 5 1 . 8 2 . 0 2 . 5 3 . 0 3 . 5 4 . 5

25 + + + + + + + + + + + 0 . 4 0 . 6 - 0 . 9 ā–  1 . 7 ' 2 . 0 2 . 3 2 . 8 3 . 3 3 . 8 4 . 9

30 15 + + + + + + + + + + + 0 . 4 ā€¢ 0.6 1 . 0 1..9 2 . 2 . 2 . 5 3 . 1 3 . 6 4 . 2 5 . 3

35 + + + + + + + + + + + 0 . 5 0 . 7 1 . 1 2 . 1 2 . 3 2 . 7 3 . 4 3 . 9 4 . 4 5 . 7

40 ā€¢ 20 + + + + + + + + ' + + + 0 .5 ' 0 .7- 1 . 1 2 . 2 2 . 4 2 . 8 3 . 6 4 . 1 4 . 9 6 . 1

50 25 + + + + + + + + + + + 0 . 5 0 . 8 1 . 3 2 . 4 2 . 7 . 3 . 2 4 . 0 4 . 5 * 5 . 5 * 6 . 9

GO 30 ā€˜ + + + + + + + + * + 0 . 6 0. 9 1 . 5 2 . 5 3 . 1 3 . 6 4 . 5 5 . 2 6 . 0 7 . 7

80 40 + + + + + + + + + + + 0 . 6 1 . 0 1 . 6 2 . 7 3 . 5 4 . 0 5 . 0 5 . 9 6 . 7 8 . 6

100 50 + + + + + + + ā€¢ + + + + 0 . 7 1 . 2 1 . 8 3 . 0 3 . 9 4 . 5 5 . 5 6 . 6 7 . 4 9 . 5

- 2 + + + + + + + + + ' + + 0 . 3 0 . 4 0 . 5 0 . 7 0 . 9 1 . 0 1 . 2 . 1 . 4 1 . 5 2 . 0- - 5 + + + + + + + + 0 . 3 0 . 3 0 . 4 0 . 5 0 . 6 0 . 8 1 . 1 1 . 3 1 . 5 1 . 9 2 . 2 2 . 4 3 . 2

1 10 + + + + + + 0 . 3 0 . 3 0 . 4 ā€¢ 0 . 5 0 . 5 0 . 7 ā€¢ 0 . 9 1 . 1 1 . 6 1 . 9 2 . 2 2 . 7 3 . 1 3 . 5 4 . 5

2 20 + + + + 0 . 3 0 . 4 0 . 4 0 . 5 ā–  0 . 6 0 . 7 1 . 0 1 . 2 1 . 5 2 . 2 2 . 7 3 . 1 4 . 0 4 . 4 4 . 9 6 . 3

3 30 + + + + + 0 . 4 0 . 5 0 . 5 0 . 6 . 0 . 7 0 . 8 1 . 2 1 . 5 1 . 9 2 . 7 3 . 3 3 . 8 4 . 9 5 . 4 6 . 0 7 . 7

4 40 + + + 0 . 3 0 . 4 0 . 6 0 . 6 0 . 7 0 . 8 ' 0 . 9 ' 1 . 4 1 . 7 2 . 2 3 . 2 3 . 8 4 . 4 5 . 5 6 . 2 6 . 9 8 . 9

5 50 + + + + 0 . 4 0 . 5 0 . 6 0 . 7 0 . 8 0 . 9 1 . 0 1 . 6 1 . 9 2 . 4 3 . 5 4 . 2 4 . 9 6 . 0 6 . 9 7 . 7 1 0 . 0

6 60 + + + 0 . 3 0 . 4 0 . 6 0 . 7 0 . 8 0 . 9 1 . 0 1 . 2 . 1 -7 2 . 1 2 . 6 3 . 8 4 . 7 5 . 5 6 . 5 7 . 7 8 . 3 1 1 . 0

III 8 80 + + + 0 . 4 0 . 5 0 . 7 0 . 8 0 . 9 1 . 0 ā€¢ 1 . 2 M 1 . 9 2 . 4 3 . 1 4 . 3 5. 5 6 . 0 7 . 5 8 . 5 1 0 . 0 1 3 . 0

10 10 0 + + + 0 . 4 0. 5 0 . 7 0 . 9 1 . 0 1 . 1 ā€¢ 1 . 3 1 . 6 2 . 2 2 . 8 3 . 5 4 . 9 6 . 0 7 . 1 8 . 8 1 0 . 0 1 1 . 0 1 4 . 0

15 15 0 + + 0 . 3 0 . 5 - 0 . 6 0 . 9 1 . 1 1 . 2 1 . 3 1 . 6 1 . 8 2 . 7 3 . 3 4 . 2 6 . 0 7 . 4 8 . 3 1 0 . 0 1 2 . 0 1 3 . 0 1 7 . 0

20 200 + + 0 . 4 0 . 5 0 . 7 1 . 0 1 . 2 1 . 4 1 . 5 ā–  r . s 2 . 0 3 . 2 3 . 9 4 . 9 6 . 9 8 . 5 1 0 . 0 1 2 . 0 1 4 . 0 1 6 . 0 2 0 . 0

25 250 + + . 0 . 4 0 . 6 0/8 1 . 2 1 . 3 1 . 6 1 . 7 2 . 0 2 . 3 3 . 5 4 . 3 5 . 5 7 . 7 1 0 . 0 1 1 . 0 1 4 . 0 1 6 . 0 1 8 . 0 - 2 3 . 0

30 300 + 0 . 5 0 . 7 0 . 8 1 . 3 1 . 4 1 . 7 1 . 9 ' 2 . 2 2 . 5 3 . 8 4 . 7 6 . 0 ' 8 . 3 1 1 . 0 1 2 . 0 1 5 : 0 1 7 . 0 1 9 . 0 .2 5 . 0

35 350 + 0 . 3 0 . 5 0 . 8 0 . 9 1 . 4 1 . 5 1 . 8 2 . 1 2 . 4 2 . 7 4 . 1 5 . 1 6 . 3 9 . 3 1 2 . 0 1 2 . 0 1 6 . 0 1 8 . 0 2 1 . 0 2 7 . 0

40 400 + 0 . 3 0 . 6 0 . 8 0 . 9 1 . 5 1 . 6 1 . 9 2 . 2 1 . 2 . 5 2 . 8 4 . 3 5 . 5 6 . 9 1 0 . 0 1 2 . 0 1 3 . 0 1 7 , 0 2 0 . 0 2 2 . 0 ā€˜ 2 8 . 0

50 500 + 0 , 4 0 . 6 0 . 9 1 . 1 1 . 6 1 . 9 2 . 1 2 . 4 2 . 8 3 . 2 4 . 7 6 . 0 7 . 5 1 1 . 0 1 3 . 0 1 5 . 0 1 9 . 0 2 2 . 0 2 5 . 0 3 2 . 0

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 74: Regulations for the Safe Transport of Radioactive Materials

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 75: Regulations for the Safe Transport of Radioactive Materials

ANNEX I 5 7

8 . T ab le VC show s, fo r vary ing nu m bers of p ackages and c o r r e s Ā­ponding rad ia tio n in d e x es , the m inim um d is ta n c e s at w hich an e x Ā­p osure dose of 100 m r w ill be rece iv ed when the exposure period has the value stated and when th e re is su ffic ien t in terven in g sh ield ing to red u ce the exp o su re d ose ra te by a fa c to r of 10 . T h is T ab le m ay be used to d eriv e the seg reg a tio n d is ta n ce s betw een p ackag es co n ta in Ā­ing rad io activ e m a te r ia ls , and p erson s when such intervenin g sh ield Ā­ing is p re se n t.

9. A lte rn a tiv e ly , the T a b le m ay be used to d e term in e d ir e c t ly the segregation d istan ces betw een packages containing rad ioactive m ateria l, and unexposed film when th e re is su ffic ie n t in terv en in g sh ield in g to red u ce the exp o su re d ose ra te by a fa c to r of 100 .10 . As a guide in the a s s e s s m e n t of the e ffe c t of sh ield in g by w alls, n on -rad ioactiv e consignm ents, other non -rad ioactive m a te ria ls , e tc . , T ab le V E m ay be u sed . T h is T a b le g iv es the m inim um th ick n e ss of com m on m a te r ia ls which w ill attenuate g a m m a-rad ia tio n by fa c to rs of 10 to 100.11. In the p re p ara tio n of T a b le s VA to VC it has been assum ed that the packages a re arran ged in contact in a plane a re a as n early square as p o ss ib le . A ll th e se packages have been assum ed to be sp h e rica l, with a rad ius of 0 . 22 m and the rad ioactiv e m a te r ia l in each package has been assu m ed to be co n cen tra ted at a point at the ce n tre of that p ackage.12. The d istan ces quoted in T ab les VA to VC a re the m inim um which m ay be used . W here in th e se T a b le s two d is ta n ce s a re given fo r the sam e tra n sp o rt index valu e , the l e s s e r of th e s e d is ta n c e s s h a ll be applied. A ltern ative m ath em atica l m odels to the one d escribed above a re p e rm iss ib le provided that they re su lt in segregation d istan ces not le s s than th o se ca lcu la ted by the m ath em atica l m odel d e scrib e d . In p a r t ic u la r , when tra n sp o rt indexes a re used , seg reg a tio n d is ta n ce s m ay be ca lcu la ted on the follow ing b a s is :

(a) A ll the ra d io a ctiv e m a te r ia l m ay be assu m ed to be co n cen Ā­tra ted at a sin g le point ir re s p e c t iv e of the num ber of p ackĀ­ages o r th e ir s iz e . The tran sp o rt index of a group of p ackĀ­ages m ay th e re fo re be taken as the sum of the tra n sp o rt in Ā­dexes of a ll the individual packages making up the group; and

(b) It may be assum ed that the sim ple in v erse square law a p p lies .

13 . A ll seg reg a tio n d is ta n ce s , - w hether d eriv ed fro m T a b le s VA to VC o r w h eth er s e p a ra te ly c a lcu la te d , m u st be m e a su re d fro m the s u r fa c e of the package o r group o f p ack ag es co n cern e d .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 76: Regulations for the Safe Transport of Radioactive Materials

58 ANNEX I

14 . When tra n sp o rt indexes a re not used and packages of m o re than one ca te g o ry a r e tra n sp o rte d to g eth e r , it sh a ll be assu m ed th at 20 c a te g o ry II p a ck a g e s a r e eq u iv a le n t to one c a te g o ry III p a c k a g e .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 77: Regulations for the Safe Transport of Radioactive Materials

ANNEX I 59

TA BL E V D

T H E D O SE R A T E T H A T G IV E S A T O T A L D O SE O F 10 m r OR 100 m r IN V A R IO U S E X P O S U R E T IM E S

D u ra tio n o f e xp o su re D ose ra te

(m r/ h )

(h ) ' (d) 1 0 m r 1 0 0 m r

1 10 1 0 0

2 5 5 0

3 3 . 3 3 3 3 . 3

5 2 . 0 0 2 0 . 0

8 1 . 2 5 1 2 . 5

1 0 1 .0 0 1 0 . 0

1 5 0 .6 0 7 6 .0 7

20 0 .5 0 0 5 . 0 0

2 4 1 0 .4 1 7 4 . 1 7

4 8 2 0 .2 0 8 2 .0 8

72 3 0 .1 3 6 1 . 3 6

1 2 0 5 0 .0 8 3 0 . 8 3 4

2 4 0 10 0 .0 4 2 0 .4 1 7

3 6 0 1 5 0 .0 2 8 . 0 .2 7 8

4 8 0 2 0 0 .0 2 1 0 .2 0 8

7 2 0 3 0 0 . 0 1 4 0 .1 3 6

9 6 0 4 0 0 .0 1 0 0 . 1 0 4

1 2 0 0 50 0 .0 0 8 - 0 .0 8 3

2 0 0 0 80 0 .0 0 5 0 .0 5 0

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 78: Regulations for the Safe Transport of Radioactive Materials

6 0 ANNEX I

TA BLE V E

SH IE L D IN G E F F E C T O F C E R T A IN M A T E R IA L S 3-

M a te r ia l

T h ic k n e s s o f m a te r ia l (c m )

to re d u ce ra d ia tio n to fo llo w in g v a lu e s

o f o r ig in a l v a lu e o f o r ig in a l v a lu e

O rd in ary c o n s ig n m e n ts o f

w h ic h th e m e a n d e n s ity

a p p ro x im a te s to th a t o f

w a ter 8 0 1 3 5

B rick w o rk (1 . 9 g / c m 3) 4 5 8 0

O rd in ary c o n c r e te

( 2 . 3 g / c m 3) 36 66

S t e e l 11 18

Lead 6 11

a F o r 2 M eV g a m m a ra d ia tio n - broad b e a m c o n d itio n s .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 79: Regulations for the Safe Transport of Radioactive Materials

ANNEX I 6 1

TA BLE V I

M U L T IP L IC A T IO N F A C T O R F O R T H E C O N V E R SIO N O F T H E R A D IA TIO N D O SE R A T E A T 1 m F R O M TH E S U R F A C E O F A F U L L LO A D O F LO W S P E C IF IC

A C T IV IT Y M A T E R IA L S IN O R D E R TO O B T A IN TH E N U M B E R O F T H E T R A N S P O R T IN D E X

S iz e o f fu ll lo ad M u lt ip lic a t io n fa c to r

W e ig h t

(a ssu m in g a d e n s ity o f th e f u ll lo a d o f 10 t/ m 3 )

Less th a n 1 tonĀ® 1

1 to n to 1 0 0 tons 2 . 5

1 0 0 to n s to 1 0 0 0 tons 7 . 0

M e a su re m e n t

( c r o s s -s e c t io n a l a re a m e a su re m e n ts o f th e lo a d

p e rp e n d ic u la r to th e d ir e c t io n o f in te re s t)

L ess th a n 1 m 2 1

1 m 2 to 5 m 2 3

5 m 2 to ^ > 2 0 m 2 6

> 2 0 m 2 to 1 0 0 m 2 19

T h a t is 1 0 0 0 kg

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 80: Regulations for the Safe Transport of Radioactive Materials

A N N E X I I

P A C K A G IN G R E Q U IR E M E N T S P A R T I - G EN ERA L

1 -1 . G EN ERA L DESIGN F E A T U R E S

1 - 1 .1 . The packaging sh a ll be so designed that the package canbe e a s ily handled and can be p ro p e rly secu re d in o r on the conveyance during tra n sp o rt .

1 -1 . 2 . A p ack ag e o f g r o s s w eight of 10 kg o r m o re and up to50 kg sh a ll be provided with m eans of m anual handling.

1 -1 . 3 . A package of g ro ss weight in e x c e s s of 50 kg sh a ll be sodesigned as to enable safe handling by m echanical m eans.

1 - 1 .4 . A ttach m en ts provided on a p ackag e fo r the p u rp ose ofliftin g that package sh a ll be designed in accord an ce with e stab lish ed sa fe ty p r a c t ic e . The d esign should embody sa fe ty fa c to rs in re s p e c t of "s n a tc h " lift in g .

1 -1 . 5 . L iftin g attachm ents, other than those d escribed in 1 -1 . 4.above, and any other fea tu re on the ou ter su rfa ce of the packaging w hich could be used to l if t the package, sh a ll be e ith e r com p letely covered o r rem oved during tr a n s Ā­port, o r sh a ll be designed so as to support the en tire weight of the p ackage, including the ap p ro p ria te sa fe ty fa c to r s to co v e r "s n a tc h " lift in g .

1 -1 . 6 . The o u ter la y e r of packaging sh a ll be so designed as toavoid as fa r as practicab le the collection and the retention of rainw ater.

1 -1 . 7. P ackaging sh a ll be designed so that the extern al su rfacesa re fre e fro m protruding fe a tu res as fa r as p ra c tica b le . Ite m s such as r e le a s e and sam ple va lv es sh a ll be re ce sse d or p ro tected fro m dam age by s te e l guards.

1 - 1 .8 . The e x tern a l su r fa ce s of packaging shall as fa r as p ra c Ā­ticab le be so designed and finished that they may be e a s iĀ­ly decontam inated.

1 -2 . GENERAL CONSTRUCTIONAL FEA TU R ES

1 - 2 .1 . The choice of m a te r ia ls used in the construction of packĀ­aging sh a ll tak e into accou nt the v a r ia tio n s in te m p e ra tu re

62

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 81: Regulations for the Safe Transport of Radioactive Materials

ANNEX II 6 3

to which such packaging m ay be su b je ct during tran sp o rt or s to ra g e . In th is re sp e c t - 4 0 Ā° C and 70Ā° C sh a ll be conĀ­sid ered as s a tis fa c to ry lim its . In re sp e c t of cold b r itt le fra c tu re , m a te r ia l with c h a r a c te r is t ic s equivalent to those of a m ild s te e l, the com p osition of which is g ^ e n h e r e Ā­under, is co n sid ered s a t is fa c to ry in the co n stru ctio n of p a ck ag es .

C H E M IC A L C O M P O S IT IO N O F M IL D S T E E L

Elem ent M axim um(Wt .Ā°}o)

Carbon 0 .2 5

Copper

Sulphur 0 .0 6 0

Phosphorus 0 .0 6 0

The package sh a ll be cap ab le of w ithstanding the e ffe c ts of any a c c e le ra t io n , v ib ra tio n , o r v ib ra tio n re s o n a n ce , which a r is e during tran sp o rt without any d eterio ra tio n in the e f fe c t iv e n e s s of the c lo s in g d e v ic e s on th e v a r io u s re c e p ta c le s o r in the in teg rity of the package as a whole. In p a rticu la r nuts, bolts and other secu rin g d ev ices shall be so designed as to p rev en t them fro m b eco m in g lo o se o r b eing re le a s e d u n in tentionally .

P A R T II - CO N TAIN M ENT AND RADIATION SH IELD IN G DESIGN P R IN C IP L E S

The d esign sh a ll include a leak p ro o f containm ent v e s s e l s e c u re ly c lo sed by a p o sitiv e fa s te n in g d ev ice w hich cannot be opened unintentionally o r by p re s s u re lia b le to a r is e in sid e the v e s s e l .The containm ent v e s s e l and its c lo s in g d ev ice s sh a ll be con stru cted of m a te r ia ls which w ill be re s is ta n t to c o r Ā­ro s io n by the contents of the package.The. d esig n o f the containm ent v e s s e l sh a ll take into accou nt the ra d io ly tic d eco m p o sition of liqu id s o r o th er vu ln erab le m a te r ia ls .The containm ent v e s s e l sh a ll be o f su ffic ien t stren gth to rem ain leakproof under the reduction of ambient p ressu re to 0.-5 atm (absolute).

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 82: Regulations for the Safe Transport of Radioactive Materials

6 4 ANNEX II

I I - l . 6.

I I - l . 7 .

I I - l . 8.

I I - l . 9.

I I - l . 5 .

I I - l . 10.

I I - l . 11.

A containm ent v e s s e l which is a sep arate unit of any packĀ­aging shall be capable of being secu re ly closed by a posiĀ­tiv e fa s te n in g d ev ice w hich is independent of any o th er p a rt of the packag in g .T h e con tain m en t v e s s e l fo r liq u id s and g a s e s s h a ll be co n stru cte d o f m e ta l.The d esig n of the packaging sh a ll take in to accou nt the n e c e s s ity of en su rin g that no build-up of in te rn a l p r e s Ā­s u re su ffic ie n t to d isru p t the containm ent v e s s e l can o ccu r .The containm ent v e s s e l sh a ll, i f n e c e s s a ry , be provided with a radiation shield e ith er inside or outside the v e sse l, o r the v e s s e l i t s e l f m ay be so d esigned a s to co n stitu te the sh ie ld .A rad ia tio n sh ield which e n c lo s e s a containm ent v e s s e l sh a ll be so d esigned as to prevent the unintentional r e Ā­le a s e of that v e s s e l and, w here the rad ia tio n sh ield and the containm ent v e s s e l within it form a sep arate unit, the rad iation shield sh a ll be capable of being secu re ly closed by a positive fastening device which is independent of any other packaging s tru ctu re .The d esign of packaging in which the rad ia tio n shielding p ro p e rty depends w holly o r p a rtly upon a d is ta n ce b e Ā­tw een the containm ent v e s s e l and the e x te r io r of the packaging, sh a ll be such that the d istan ce is m aintained . P ackaging which includes heat insu lation fo r the purpose of co n fo rm in g to the Type B packaging re q u ire m e n ts sp e c ifie d in C - 2 . 3. sh a ll be so designed that in su latin g m a te r ia l on the e x te r io r of the package o r p ackaging s tru c tu re providing heat in su latio n would re m a in e f fe c Ā­tive i f the package w ere su b jected to the te s ts sp ecified in Annex IV , 1 -2 . and 1 -4 .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 83: Regulations for the Safe Transport of Radioactive Materials

A N N E X I I I

F IS S IL E M A T E R IA L S : M E T H O D S OF C O M P L IA N C E W IT H N U C L E A R S A F E T Y C R IT E R IA

P A R T I - F IS S IL E CLA SS I PACKAGES

1 -1 . SCH EM ES O F CALCU LA TION .

1 - 1 .1 . S c h e m e 1 1

(a) E a c h individual package sh a ll com ply with the c r i Ā­t e r ia under C - 5 . 3 . 1 . 1 . (a ).

(b) The package, w hether damaged o r undamaged, sh a ll be such as to shield the f is s i le contents from therm al neutrons;

(c) W hen a p a r a l le l beam of n eu trons having an en ergy sp e ctru m as sp e cifie d in the T ab le below is incid ent at any angle on an undam aged p ackage, the su r fa c e m u ltip lica tio n fa c to r fo r e p ith erm a l n e u tro n s, i . e . the ra tio of the num ber of ep ith erm al neutrons le a v Ā­ing the package to the num ber of ep itherm al neutrons en tering the package, sh a ll be le s s than one, and the energy sp ectru m of the neutrons that a re em itted by the p ackage in an in fin ite a r r a y sh a ll be no h a rd e r than th at of the in cid en t n e u tro n s ; and

(d) C o m p lian ce w ith C - 5 . 3 . 1 . 2. (b) above s h a ll be d e m o n s tra te d .

65

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 84: Regulations for the Safe Transport of Radioactive Materials

6 6 ANNEX III

N E U T R O N E N E R G Y S P E C T R U M a T O B E U SE D IN S C H E M E 1

N eutron en e rg y

E

F r a c tio n o f n eu tron s

w ith e n e rg y le ss th a n E

1 1 . 0 M eV 1 . 0 0 0

2 . 4 M eV 0 . 8 0 2

1 . 1 M eV 0 . 5 9 0

0 . 5 5 M eV 0 . 4 6 0

0 . 2 6 M eV 0 . 3 7 3

0 . 1 3 M eV 0 . 3 1 9

4 3 M eV 0 . 2 6 3

1 0 k eV , 0 . 2 1 0

1 . 6 k eV 0 . 1 5 6

0 . 2 6 keV 0 . 1 1 1

4 2 eV 0 . 0 7 2

5 . 5 eV 0 . 0 3 6

0 . 4 eV 0

a T h e sp e c tru m is th e e p ith e r m a l p o rtio n o f th e e q u ilib r iu m sp ec tru m e m e rg e n t from

p a c k a g e s in c o rp o r a tin g 5 c m th ic k n e s s o f w ood in a c r i t i c a l a rra y o f su ch p a c k a g e s .

1 -2 . PH YSIC A L M O D ELS

1 - 2 . 1 . M o d e l N o . 11 - 2 .1 .1 . P ackaging

(a) The packaging is constru cted so that the f is s i le conĀ­ten ts a re surrounded by a la y e r of m a te r ia l capable of absorbing a ll th e rm a l neutrons incident on it* and th is neutron ab so rben t la y e r is then surrounded by a th ickness of at le a s t 10. 2 cm . of wood having a m iniĀ­mum hydrogen content of 6. 5 w t.%, so that the m in iĀ­mum e x te rn a l d im ension o v er the wood is 30 . 5 cm .

(b) The packaging is so con stru cted that under the conĀ­d itio n s re p re s e n te d by te s ts in A nnex IV , 1 -2 . and 1 -4 . - the f i s s i l e co n ten ts w ill re m a in surrounded by the neutron absorbent lay er, the neutron absorbent la y e r w ill rem ain surrounded by the wood, wood w ill not be lo st to an extent which would reduce the th ickĀ­

* This layer can consist of cadmium at least 0. 38 mm thick equivalent to 0 .3 2 5 g Cd/cā€™m!

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 85: Regulations for the Safe Transport of Radioactive Materials

ANNEX III 67

n ess of the rem aining wood to le s s than 9. 2 cm or to reduce the minimum extern al dim ension over the r e Ā­maining wood to le s s than 28. 5 cm .

1 - 2 .1 .2 . ContentsT he con ten ts do not exceed the p e rm is s ib le m a ss of f is s i le m a te r ia l shown by that entry in T ab les I to X which

. is co n sisten t with the nature of the m a te r ia l and with the m ax im u m m o d e ra tio n and th e m ax im u m d ia m e te r (o r volum e) w hich could o ccu r if the pack age w ere s u b je c t to the con d ition s re p re se n te d by th e te s t s in A nnex IV , 1 -2 . and 1 -4 .Note: F o r the values given in T ab les I to X , calculations

w ere used which w ere based on Annex II of ReguĀ­lations fo r the Safe T ran sp o rt of Radioactive m aĀ­te r ia ls IAEA, Safety S e r ie s No. 6, (1961) and which a re r e s tr ic t iv e by co m p ariso n with Schem e 1 of I ā€”1 .1 . above. Hence, the values can be used safeĀ­ly in a s s o c ia tio n with packaging com plying with the d e s cr ip tio n in 1 - 2 .1 . 1 . although a : d eta iled ca lcu la tio n of p e rm is s ib le v alu es in a cco rd a n ce w ith S ch em e 1 of I ā€”1. 1 . above m ay y ie ld l e s s r e s t r ic t iv e v a lu e s fo r the sa m e p ack ag in g .

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 86: Regulations for the Safe Transport of Radioactive Materials

TABLE I

A Q U EO U S SO L U T IO N S O F P L U T O N IU M N IT R A T E

Permissible mass of plutonium nitrate per package as a function of ihe packaging wood density

05CO

1 .1. Limited by maximum internal diameter of inner receptacle

Innerreceptacle diameter not

Wood density not exceeding 1 .2 5 g/cm3 and not less than (g/cm3) 0 .6 0 .6 5 0 .7 0. 75 0 .8 0 .8 5 0 .9 0 .95 1.0 1. 05 1.1 . 1 .15 1.2 1 25

exceeding(cm) kg Pu(NOs)4 per package

10.16 M o l i m i t

No lim it 0 .044 0. 108 0 .171 0.232 0.291 0.348 0 .4 0 0.46 0 .5 1 0.55 0 .5 9 0 .6 3 0.66 0 69

I. 2 . Limited by maximum internal volume of inner receptacle

Innerreceptacle volume not

Wood density not exceeding 1 .2 5 g/cm3 and not less than (g/cm3) 0 .6 0 .6 5 0 .7 0 .7 5 0 .8 0 .8 5 0 .9 0. 95 1.0 1.05 1.1 1.15 1.2 1 25

exceeding(1) kg Pu(No3) 4 per package

2 0.310 0 .6 1 1.06 1. 64 2 .3 7 3 .2 4 9.2 9 .2 9 .2 9 .2 9 .2 9 .2 9 .2 9 .2

3 0. 096 0.271 0 .5 0 0. 77 1 .42 1 .55 9 .2 9 .2 9 .2 9 .2 ā€¢ 9 .2 9 .2 9 .2 9 24 0. 044 0.155 0. 193 0.271 1.42 1.42 1.42 1.42 1.42 1. 82 2 .4 4 3 .1 7 4 .0 4 5 03

5 0,044 0.108 0. 173 0.240 1.42 1.42 1.42 1.42 1.42 1.42 1.42 1.42 1.42 1 42

7 0. 044 0. 108 0.171 0.232 1.42 1.42 1.42 1.42 1.42 1.42 1.42 1.42 1.42 142

No lim it 0 .044 0. 108 0. 171 0.232 0 .291 0. 348 0 .4 0 0 .4 6 0.51 0. 55 0 .59 0.63 0.66 0 69

ANNEX III

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 87: Regulations for the Safe Transport of Radioactive Materials

TABLE II

A Q UEO US SO L U T IO N S O F U R A N Y L a F L U O R ID E O R U R A N Y L a N IT R A T E

Permissible mass of uranium per package as a function of the packaging wood density

II. 1. Limited by maximum internal diameter of inner receptacle

Wood density not exceeding 1 .25 g/cm and not less than (g/cm3)0 .6 0 .65 0 .7 0 .7 5 .0.8 0 .8 5 0 .9

Innerreceptacle diameter not exceeding(cm) kg uranium per package

10.16 i ---------------------------------------------------------------------------------------------------------- No l i m i t --------------------------------------------------------------------------------------------------

N olim it 0 .0 8 4 0 .120 0 .1 5 7 0 .193 0 .231 0 .2 6 7 0 .3 0 1 0 .335 0 .3 7 0 0 .400 0 .4 2 9 0 .4 5 6 0 .478 0 .4

II. 2 . Limited by maximum internal volume of inner receptacle

Innerreceptacle volume not exceeding (1)

Wood density not exceeding 1 .2 5 g/cm3 and not less than (g/cm9)0 .6 0 .6 5 0 .7 0 .7 5 0 .8 0 .8 5 0 .!

kg uranium per package

0 .9 5 1 .0 1 .0 5 1 .1 1 .1 5 1 .2

2 0.152 0.380 0.66 1.01 1.47 2.00 2. 66 3. 50 4 .6 4 6 .04 7.62 9. 39 11 .3 13 .3

3 0.084 0.223 0.416 0 .6 5 0.93 1.25 1. 58 1 .96 2 .3 4 2 .7 4 3 .1 6 3 .5 7 3 .9 9 4 .4 2

4 0.084 0.120 0 .157 0.193 0.231 0 .274 0 .356 0.498 0. 73 1. 05 1 .47 2.02 2. 70 3. 55

5 0. 084 0.120 0.157 0.193 0.231 0 .267 0. 301 0.495 0.57 0.66 0. 74 0 .8 4 0 .92 1.027 0.084 0.120 0.157 0.193 0.231 0,267 0 .301 0. 347 0.406 0.467 0.53 0. 60 0.66 0 .7 3

> lim it 0.084 0.120 0.157 0.193 0.231 0.267 0 .301 0. 335 0.370 0.400 0.429 0 .456 0.478 0.498

a Uranium which includes no Um and no more than 93? m .% U135

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 88: Regulations for the Safe Transport of Radioactive Materials

TABLE III - JONON-HYDEOGENOUS URANIUM3 COMPOUNDS OR M IXTU RES IN WHICH THE URANIUM -235

CONCENTRATION DOES NOT E X C E E D -4 .8 g/cm3b

(Including unmoderated uranium metal of uranium-235 enrichment not exceeding 25 wt.^o)

Permissible mass of uranium per package as a function of the packaging wood density

III. 1 Limited by maximum internal diameter of inner receptacle

Inner Wood density not exceeding 1 .2 5 g/cm3 and not less than 0 .6 g/cm3receptaclediameter not

(cm) kg uranium per package ------------

10. 16 No l i m i t

No lim it 0 .6 9

III. 2 Limited by maximum internal volume of inner receptacle

Inner Wood density not exceeding 1 .25 g/cm3 and not less than (g/cm3)rec ep tac le 0. 65 0. 7 0. 75 0.8 0.85 0 .9volume not ā€” ---------------- ---------exceeding(1) kg uranium per package

3 7 .0 10.0 12.2 14.5 14.5 14 .54 4 .8 7 .8 7 .8 7 .8 7 .8 7 .85 3 .6 3 3 .6 3 3 .6 3 3 .6 3 3.63 3. 637 1.41 1 .41 1 .41 1 .41 1.41 1.41

No lim it 0 .6 9 0 .6 9 0 .6 9 , 0 .6 9 0 .6 9 0 .6 9

a Uranium which includes no U*33 and no more than 93{ wt.% U2JSb Mixtures containing beryllium or deuterium are excluded and the mass of carbon must not exceed five times the allowed mass of uranium.

ANNEX III

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 89: Regulations for the Safe Transport of Radioactive Materials

TABLE IV

NON-HYDROGENOUS URANIUMa COMPOUNDS OR M IXTU RES IN WHICH THE URANIUM -235 CONCENTRATION DOES NOT E X C E E D 9. 6 g/cm 3b

(Including unmoderated uranium metal of uranium-235 enrichment not exceeding 50 wt.*7o)

Permissible mass of uranium per package as a function of the packaging wood density

IV . 1. Limited by maximum internal diameter of inner receptacle

Innerreceptacle diameter not

Wood density not exceeding 1 .25 g/cm3 and not less than (g/cm3)0 .6 0 .6 5 0. 7 0 .7 5 0 .8 0 .8 5 0 .9 0 .95 1.0 1. 05 1 .1 1 .15 1.2 1.25

exceeding(cm) kg uranium per package

7 .5 88 .5

66 7 8

9 .2 109 .2 109 .2 10 0 .6 9 0 .69

11 12 14 11 12 14

0 .6 9 0 .6 9 0 .6 9

1515

0 .6 910

No limit60 .6 9

7 8 0 .6 9 0 .69

160 .6 9

17 17 0 .6 9 0 .6 9

170 .6 9

190. 69

fc

IV. 2 . Limited by maximum internal volume of inner receptacle

Innerreceptacle volume not

Wood density not exceeding 1 .2 5 g/cm3 and not less than (g/cm3)0 .6 5 0 .7 0 .7 5 0 .8 0 .85 0 .9 0. 95 1.0

exceeding(1)

345 7

No lim it

74 .83 .6 31 .410 .69

87.8 3 .63 1.41 0. 69

9 .27 .83 .631 .410 .69

10 11 7 .8 7 .8 3 .6 3 3 .63 1 .4 1 1.41 0 .6 9 0 .6 9

12 7 .8 3. 63 1 .41 0 .6 9

147 .83 .631 .410 .6 9

1 4 .57 .83 .6 31 .410 .6 9

a Uranium which includes no U233 and no more than 93Ā£ wt.*7o U 235k Mixtures containing beryllium or deuterium are excluded and the mass of carbon must not exceed five times the allowed mass of uranium.

annex m

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 90: Regulations for the Safe Transport of Radioactive Materials

TABLE V

U N M O D E R A T E D U RA N IU M a M E T A L

Permissible mass of uranium per package as a function of the packaging wood density

V. 1. Limited by maximum internal diameter of inner receptacle

Innerreceptacle diameter not

Wood density not 0 .6 0 ,6 5

exceeding 1 .25 g/cm 0 .7 0 .7 5

and not less than (g/cm3) 0 .8 0 .8 5 0 .9 0 . 95 1.0 1.05 1.1 1 .1 5 1.2 1.25

exceeding(cm) kg uranium per package

-----------ā€”

No l i m i t6 .57

l i m i t6 9 .2 10 ā€¢

7 .5 6 8 9 .2 10 11 12 14 15 16 17 17 17 1910 6 8 9.2 10 11 12 14 15 16 17 17 17 19

No lim it 0 .6 9 0 .69 0 .6 9 0 .6 9 0. 69 0. 69 0. 69 0 ,6 9 0 .6 9 0 .6 9 0 .6 9 0 .6 9 0 .6 9 0 .6 9No lim it k 6 8 9 .2 10 11 12 14 15 16 17 17 17 19

V. 2. Limited by maximum internal volume of inner receptacle

Innerreceptacle volume not

Wood density not exceeding 1 .2 5 g/cm3 0 .6 0 .6 5 0 .7 0 .7 5

and not less than (g/cm3) 0 .8 0 .8 5 0 .9 0. 95 1.0 1. 05 1.1 1.15 1.2 1 .2 5

exceeding(1) kg uranium per package

2 6 7 8 9.2 10 11 12 14 15 16 17 17 17 193 6 8 9.2 10 11 12 14 14 .5 14 .5 14 .5 14 .5 14 .5 1 4 .54 6 7 .8 7 .8 7 .8 7 .8 7 .8 7 .8 7 .8 7 .8 7 .8 7 .8 7 .8 7 .85 3 .6 3 3. 63 3 .6 3 3 . 63 3 . 63 3. 63 3 .6 3 3 . 63 3. 63 3. 63 3 .6 3 3 .63 3 .6 3 3 .6 37 1.41 1.41 1.41 1.41 1.41 1.41 1.41 1.41 1.41 1.41 1.41 1.41 1.41 1.41

No lim it 0 ,6 9 0 .69 0 .6 9 0. 69 0 .6 9 0 .6 9 0 .6 9 0 .6 9 0 .6 9 0 .6 9 0 .6 9 0 .6 9 0 .6 9 0 .6 9No lim it^ 6 7 8 9 .2 10 11 12 14 15 16 17 17 17 19

a Uranium which includes no U233 and no more than 93Ā£ wt.^o U 235k These enhanced masses apply where the fissile material is in the form of massive metal pieces weighing not less than 2 kg each and free from re-entrant surfaces.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 91: Regulations for the Safe Transport of Radioactive Materials

TABLE VI

URANIUM3- COMPOUNDS OR M IX TU R ES IN WHICH THE URANIUM CONCENTRATION DOES NOT E X C E E D TTlā€ž VH/U+1.41

Permissible mass of uranium per package as a function of the packaging wood density

?fi 44

VI. 1. Limited by maximum internal diameter of inner receptacle

Wood density not exceeding 1 .2 5 g/cm and not less than (g/cm )0 .6 0 .6 5 0 .7 0 .7 5 0 .8 0 .8 5 0 .9

Innerreceptacle diameter not exceeding(cm) kg uranium per package

6 .5 2 .8 02 .8 02 .8 0

6.06.06.0

6.06.0

6.06.0

6.06.0

No l i m i tri r

----------- Ā»

7.5 6.0 6.0 14 15 15.2 15.2 15 .2 15 .2 15.210 0.330 0 .8 7 1.10 1.80 2. 50 3 .50 4 .6 7 .1 7 .7 9 .6 11.6 13.8 16 .1 18 .3

No lim it 0. 084 0.120 0.157 0.193 0.231 0.267 0 .301 0.335 0 .3 7 0 0 .400 0.429 0 .456 0 .478 0.498

VI. 2. Limited by maximum internal volume of inner receptacle

Innerreceptacle volume not exceeding (1)

Wood density not exceeding 1 .25 g/cm3 and not less than (g/cm 3) 0 .6 0 .6 5 0 .7 0 .7 5 0 .8 0 .8 5

kg uranium per package

2 0. 152 0.380 0. 66 1.01 1.47 2.00 2.66 3 .5 0 4 .6 4 6. 04 7. 62 9 .3 9 11 .3 13 .33 0. 084 0.223 0.416 0. 65 0. 93 1 .25 1 .58 1. 96 2 .3 4 2 . 74 3. 16 3 .5 7 3 .9 9 4 .4 24 0.084 0. 120 0.157 0. 193 0 .231 0.274 0.356 0.498 0.73 1.05 1.47 2.02 2 .7 0 3 .5 55 0.084 0.120 0.157 0. 193 0.231 0.267 0 .301 0.495 0. 57 0.66 0. 74 0 .8 4 0. 92 1.027 0. 084 0.120 0. 157 0.193 0.231 0.267 0 :301 0.347 0 .406 0.467 0. 53 0. 60 0. 66 0. 73

lim it 0. 084 .0 .1 2 0 0. 157 0. 193 0.231 0.267 0.301 0.335 0 .370 0.400 0.429 0 .456 0.478 0 .498

a Uranium which includes no U233 and no more than 93^ wt.% U 23S

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 92: Regulations for the Safe Transport of Radioactive Materials

TABLE VII

NON-HYDROGENOUS PLUTONIUM COMPOUNDS OR M IXTU R ES IN WHICH THE PLU TO N IU M -239 CONCENTRATION DOES NOT E X C E E D 1 0 g / cm 3a

Permissible mass of plutonium per package as a function of the packaging wood density

VII. 1. Limited by maximum internal diameter of inner receptacle

Innerreceptacle diameter not

Wood density not exceeding 1 .25 g/cm3 and not less than (g/cm3) 0 .6 0 .6 5 0 .7 0 .7 5 0 .8 0 .9 5 1. 05 1.1 1.15 1.25

exceeding(cm) kg plutonium per package

6 .5 3 .6 0 4 .23 .6 0 4 .23 .6 0 4 .23 .6 0 4 .2 0 .405 0 .405

N 1* ' t4 . 74 .74 .7 0.405

5 .35 .35 .3 0 .405

o lm iXT - 1 .

7 .5 ā€¢ 10

No lim it

5 .95 .9 0.405

7 .17 .1 0.405

fJo I ' m i t8.10.405

8 .30 .405

8.60.405

8 .9 0 .405

VII. 2. Limited by maximum internal volume of inner receptacle

Innerreceptacle volume not

Wood density not exceeding 1 .2 5 g/cm3 and not less than (g/cm3) 0 .6 0 .6 5 0ā€ž 7 0 .7 5 0.8

exceeding(1) kg plutonium per package

345 7

No lim it

3. 60 3 .6 0 2 .4 4 1.20 0.405

4 .23 .8 42 .4 41.200.405

4. 7 3 .8 4 2 .4 4 1.20 0.405

5 .33 .8 42 .4 41.200.405

5.3. 84 2 .4 4 1.20 0.405

a Mixtures containing beryllium and deuterium are excluded and the mass of carbon must not exceed 1/10 of the allowed mass of plutonium.

ANNEX III

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 93: Regulations for the Safe Transport of Radioactive Materials

TABLE VIII

U N M O D ER A TED P L U T O N IU M M E T A L

Permissible mass of plutonium per package as a function of the packaging wood density

VIII. 1. Limited by maximum internal diameter of inner receptacle

Innerreceptacle diameter not exceeding (cm )

Wood density not exceeding 1 .25 g/cm3 and not less than (g/cm3) 0 .6 0 .6 5 0 .7

kg plutonium per package

10 No lim it No lim ita

3 .203 .20 0.4053.20

3 .6 0 0 .4053 .6 0

3. 90 0 .405 3. 90

4 .2 0.4054 .2

4 .4 0 .4054 .4

4 .5 0.4054 .5

VIII. 2. Limited by maximum internal volume of inner receptacle

Innerreceptacle volume not exceeding(D

Wood density not exceeding 1 .25 g/cm3 and not less than (g/cm3) 0 .6 0 .6 5 0 .7

kg plutonium per package

3 3.20 3. 60 3 .9 0 4 .2 4 .4 4 .54 3 .2 0 3 .6 0 3 .8 4 3. 84 3 .8 4 3 .8 45 2 .4 4 2 .4 4 2 .4 4 2 .4 4 ā€¢ 2 .4 4 2 .4 47 1.20 1.20 1.20 1.20 1.20 1.20

No lim it 0 .405 0.405 0.405 0.405 0.405 0.405No-limita 3 .2 0 3 .6 0 3 .9 0 4 .2 4 .4 4 .5

These enhanced masses apply where the fissile material is in the form of massive m etal pieces weighing not less than 2 kg each and free from re-entrant surfaces.

ANNEX III

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 94: Regulations for the Safe Transport of Radioactive Materials

PLUTONIUM COMPOUNDS OR M IXTU RES IN WHICH THE PLUTONIUM CONCENTRATION DOES NOT E X C E E D ā– -----2 6 ' 5 6 ~H/Pu+1. 35

Permissible mass of plutonium per package as a function of the packaging wood density

IX. 1. Limited by maximum internal diameter of inner receptacle

Innerreceptacle diameter not

Wood density not 0. 6 0. 65

exceeding 1 .2 5 g/cm3 0 .7 0 .75

and not less than (g/cm3; 0 .8 0 .8 5 0 .9 0 .95 1.0 1.05 1.1 1.15 1.2 1.25

exceeding(cm) kg plutonium per package

3 .2 3 .60 3. 90 4 .2 4 .4 1 ā€¢ 'r6 2 .8 0 3. 60 3 ā€™ 90 4 .2 4 .4 4 .5 4 .5 4 .5 4 .5 4 .5 4 .5 4 .5 4 .5 4 .56. 5 2 .5 0 3 .40 3. 80 4 .2 4 .4 4 .5 4 .5 4 .5 4. 4. 4 .5 4. 5 4 . 5 4 .57 2.20 3. 10 3. 70 4 .2 4 .4 4 .5 4 .5 4 .5 4 .5 4 .5 4 .5 4 .5 4 .5 4 .57 .5 1. 90 2 .7 0 3 .4 0 4 .1 4 .4 4 .5 4 .5 4 .5 4 .5 4 . 5 4 .5 4 .5 4 .5 4 .58 1 .60 2 .3 0 3 .0 3 .80 4 .4 4 .5 4 .5 4 .5 4 .5 4 .5 4 .5 4 . 5 4 .5 4 .58 .5 1 .30 1 .80 2 .4 0 3 .2 0 3 .8 0 4 .3 4 .5 4 .5 4 .5 4 .5 4 .5 4 .5 4 .5 4. 59 0. 97 1 .30 1.80 2 .4 0 3. 00 3 .4 0 3 .6 0 3.80 4 .0 4 .2 4 .4 4 .4 4 .4 4.'49 .5 0 .65 0.88 1.20 1.50 1.90 2.20 2 .4 0 2 .6 0 2 .8 0 3 .1 0 3.60 4 .4 4 .4 4 .4

10 0.330 0.42 0 .5 0 0. 58 0. 70 0 .83 0. 99 1.20 1. 50 1. 90 2 .7 0 3 .9 0 4 .5 4 . 5No lim it 0. 022 0.053 0.084 0.114 0.143 0 .171 0.199 0.226 0.250 0.274 0.294 0.311 0 .327 0.339

IX .2 . Limited by maximum internal volume of inner receptacle

Innerreceptacle

Wood density not 0 .6 0 .65

exceeding 1 .2 5 g/cms 0 .7 0 .75

and not less than (g/cm3) 0 .8 0 .85 0 .9 0 .9 5 1.0 1. 05 1.1 1.15 1.2 1.25

exceeding(1) kg plutonium per package

2 0.152 0. 309 0. 52 0 .80 1.16 1.59 4 .5 4 .5 4 .5 4. 4 .5 4 . 5 4 .5 4 .53 0 .047 0.133 0.247 0. 380 0. 700 0. 76 4 .5 4 .5 4 .5 4 .5 4 .5 4 .5 4 .5 4 .54 0.022 0. 076 0.095 0.133 0.700 0. 700 0.700 0. 700 0 .700 0 .8 9 1.19 1.55 1. 98 2 .4 75 0.022 0. 053 0.085 0.118 0.700 0. 700 0. 700 0. 700 0*. 700 0. 700 0.700 0. 700 0. 700 0. 7007 0.022 0.053 0.084 0. 114 0.700 0.700 0.700 0. 700 0. 700 0. 700 0.700 0.700 0. 700 0.700

No lim it 0.022 0.053 0. 084 0 .114 0. 143 0 .171 0.199 0.226 0 .250 0 .274 0.294 0.311 0. 327 0.339

ANNEX III

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 95: Regulations for the Safe Transport of Radioactive Materials

AQUEOUS SOLUTIONS O F URANIUM -233 N ITR A TE OR U RAN IUM -233 FLU O R ID E

!Permissible mass of uranium per package as a function of the packaging wood density

TABLE X

X . 1. Limited by maximum internal diameter of inner receptacle

Inner Wood density not exceeding 1 .25 g/cm3 and not less than (g/cm3)receptacle 0 .6 0 .6 5 0 .7 0 .7 5 0 .8 0 .8 5 0 . 9 ' 0 .9 5 1 .0 1 .0 5 1 .1 1 .1 5 1 .2 1 .25diameter not ________ ________________________________exceeding ----------------------------------------------------------- --------------------(cm) kg uranium per package

9 -Ģ‚------------------------------------------------------------------------------------------------------------ No l i m i t ----------------------------------------------------------------------------------------------------->9 .5 0 .0 3 5 0 .067 <----------------------------------------------------------------------------------- No l i m i t ---------------------------------------------------------------------------------------------*

10 0 .0 3 5 0 .067 0 .100 <-----------------------------------------------------------------:------------- N o l i m i t ---------------------------------------------------------------------------------- >No lim it 0 .0 3 5 0 .067 0 .100 0 .1 3 4 0 .1 6 9 0 .200 0 .2 3 1 0 .2 6 1 0 .2 8 9 0 .3 1 6 0 .3 4 0 0 .3 6 1 0 .3 7 1 0 .3 9 1

X . 2 . Limited by maximum internal volume of inner receptacle

Innerreceptacle volume not exceeding (1)

2 0.152 0.309 0 .475 0 .7 1 0 .9 9 1.33 1.71 2.11 2 .5 4 2 .9 9 3 .4 4 3 .9 4 4 .4 1 4 .83, 0 .0 8 5 0.133 0. 180 0.228 0 .285 0.332 0 .389 0.446 0. 50 0 .5 6 0. 60 0 .6 7 0. 73 0. 784 0.085 0.109 0. 133 0.175 0.213 0.256 0 .304 0.356 0.408 0.460 0 .5 1 0 .5 7 0 ,6 3 0 .6 95 0.035 0.076 0. 114 0.152 0.190 0.223 0 .256 0.292 0.323 * 0 .356 0. 389 0 .422 0 .451 0.4847 0.035 0.073 0. 109 0. 142 0 .175 0.204 0 .235 0.263 0.289 0.318 0. 342 0.368 0 .394 0.420

No lim it 0 .035 0.067 0. 100 0.134 0 .169 0.200 0. 231 0.261 0.289 0.316 0.340 0 .361 0 .377 0.391

Wood density not exceeding 1 .2 5 g/cm3 and not less than (g/cm3)0 .6 0 .6 5 0 .7 0 .7 5 0 .8 0 .8 5 0 .9 0. 95 ā€™ 1 . 0 1 .0 5 1 .1 1 .1 5 1 .2 1 .25

kg uranium per package

- J- J

ANNEX III

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 96: Regulations for the Safe Transport of Radioactive Materials

7 8 ANNEX III

1-3. P A C K A G E DESIGNS C O M P L Y IN G W IT H FISSILE

CLASS I CRITERIA

The Agency invites the submission of package designs

which, when recognized as meeting the relevant proĀ­

visions of these regulations, will be described or reĀ­

ferred to under this heading.

The United Kingdom of Great Britain and Northern Ireland

has provided data (reproduced in the Appendix) on

U .K . A .E . A . Design No. 0493B as an indication of the

type of information which, together with detailed conĀ­

structional specifications and permissible contents, should

be included under this heading. It is also foreseen that

package designs may be included under this heading by

simple reference.

Note: Further schemes of calculation, physical models

and package designs will from time to time be inĀ­

cluded in this Part after the Agency is satisfied

that packages designed in accordance with any of

those data meet, the criteria for Fissile Class I

when mixed with other packages designed in acĀ­

cordance with any of the schemes, physical models

or package designs already provided in this Part

of Annex III.

P A R T II - FISSILE CLASS II P A C K A G E S

II-l. P A C K A G E DESIGNS C O M P L Y IN G W IT H FISSILE

CLASS II CRITERIA

The Agency invites the submission of package designs

which, when recognized as meeting the relevant proĀ­

visions of these regulations, will be described or referred

to under this heading.

A P P E N D IX

D A T A R E L E V A N T T O 1-3., A N N E X III T O T H E R E G U L A T IO N S

U .K . A . E . A . Design No. 0493B for a Fissile Class I package

for uranium metal

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 97: Regulations for the Safe Transport of Radioactive Materials

F ig . 6

F is s ile C la ss I p a c k a g e fo r uranium m e t a l 3

1 body 10 id e n t if ic a t io n la b e l

2 lid 11 t r e fo il sy m b o l la b e l

3 c a p t iv e b o lt 12 s e a l tag

4 c o v e r p la te 13 P . V . C . b ag

5 w ood sh ie ld b lo c k 1 4 tin n e d s te e l c a n

(g re e n h e a r t) (D e s ig n N o .0 5 6 4

6 sh ie ld b a rr ie r DRG N o . B 3 3 7 8 '

(c a d m iu m ) 15 in n e r c o n ta in e r

7 pressure r e l i e f v a lv e (D e s ig n N o . 0 6 5 1

8 jo in t ring DRG N o . HR/B ]

9 p a d lo c k or

D e sig n .N o . 0 8 5 2

DRG N o . B 3 2 7 4 A)

O v er- a l l d im e n sio n s:

22^ in h ig h x 1 3 in squ are

(5 7 x 3 3 x 3 3 c m )

Gross w eig h t o f p a c k a g in g :

1 8 0 lb s ( 7 2 kg)

P e rm itte d c o n te n ts e n r ic h e d u ran iu m m e ta l :E n r ic h m e n t n o t e x c e e d in g 2 5 w t. U 235 - no m ass l im i t

E n r ic h m e n t n o t e x c e e d in g 5 0 w t. % V 23S - up to 21 kg U

E n r ic h m e n t u n lim ite d - up to 1 1 . 5 kg U

T h e packaging illustrated in this exam ple is one o f the several packagings based on U. K. A . E. A. Design No. 0493 (the outer container) which are used as general purpose packagings for fissile m aterials.

This particular assem bly of outer container and inner container is specified by U. K. A. E. A. Design No. 0493 B and the perm itted contents are one exam ple of the four different kinds o f fissile m aterials for which this packaging m ay b e used.

Currently there are seven variants o f packagings based on Design No. 0493 , specified as Design Nos. 0493 A, 0493 B, e tc . These several packages have been cleared according to the requirements o f Fissile Class I for a com prehensive range o f different fissile contents, and these c learan ces could readily be extended when required to cover every kind o f fissile m ateria l.

ANNEX III

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 98: Regulations for the Safe Transport of Radioactive Materials

A N N E X I V

T E S T PRO CEDURES

P A R T I - F O R P A C K A G IN G

1-1. G E N E R A L

1-1. 1. The tests shall be applicable to samples or prototypes

of a particular packaging design. This implies that subĀ­

sequent to a satisfactory conclusion of the tests, and in

the production of packaging for use, full inspections will

be carried out to ensure that the standard of the features

proved in the prototype will be maintained.

1-1 . 2 . T h e n u m b e r o f s a m p le s o r p ro to ty p e s to b e t e s t e dIn the interests of economy and safety the number of

samples or prototypes actually subjected to the tests

should be related to the number of packagings of that

type which are to be produced and used, the frequency

of use, and the individual cost of the very expensive

packagings. For samples or prototypes of a packaging

design which will be subjected to tests a schedule of those

tests should be prepared indicating the actual tests to

be performed, their sequence and the number of samples

or prototypes required. The results of the tests may

necessitate an increase in that number of samples or

prototypes in order to meet the requirements of the test

procedures in respect of maximum damage. In some

cases the use of calculative methods will be adequate

without subjecting an actual prototype to any tests.

I - 1 . 3. P re p a ra tio n o f a p ro to ty p e p a ck a g in g fo r tes t in g1-1. 3. 1. All packaging shall be examined before testing to identify

and record faults or damage including the following:

(a) Divergence from the specifications or the drawings

of the prototype being tested;

(b) Defects in construction;

(c) Corrosion or other deterioration; and

(d) Distortion of features.

1-1.3. 2. Dirt, moisture and other contamination shall be cleaned

from the packaging.

80

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 99: Regulations for the Safe Transport of Radioactive Materials

ANNEX IV 8 1

1-1. 3. 3. Sample packages shall be made up exactly as they would

be used in transport including any external fittings,

wrappings, crates or other supplementary equipment.

The contents of the sample package shall simulate as

closely1 as practicable the radioactive material likely

to be carried in that form of packaging. The effects of

self-heating by radioactive decay may be assessed sepaĀ­

rately, but should be taken into account in evaluating the

results of both the drop and fire tests. A suitable radioĀ­

active material may be included with the contents. The

weight of the package for the purpose of the tests shall

include the contents and shall be the same as the actual

package in use.

1-1. 3. 4. The containment vessel of the packaging shall be clearly

identified.

1-1. 3. 5. The external features of a packaging shall be clearly

identified so that reference may be made simply and

clearly to any point of such packaging.

1 - 1 . 4 . T e s t i n g o f t h e I n t e g r i t y o f c o n t a i n m e n t a n d s h i e l d i n gAfter any of the tests provided for in 1-2., 1-3. and 1-4.

below, or any of the tests subsequently to be incorporated

in 1-4., have been carried out on a package, it shall be

further demonstrated that the integrity of the containment,

or of the containment and shielding, has been retained

to the extent required for the type of packaging used in

the package under test. Performance of the containment

test, or of the containment and shielding tests as indiĀ­

cated in 1-5. below, or as may subsequently be incorĀ­

porated therein, shall be one method of so demonstrating.

1-2. P R O C E D U R E S FO R T H E TESTS R E F E R R E D T O IN

C- 2.2 .1, C-5. 3. 1. 2. (a) AND (b), C-5.4 .1 .1 ,

C-5, 4 .1 . 3. (b), A N N EX II, II-l.ll. AND A N N EX III, 1-2.1.

The package shall be subjected to the effects of each test

included below unless it is specifically exempted thereĀ­

from. One sample package shall be subjected to the

consecutive application of at least two of the tests from

which it is n6t specifically exempted.

1 -2 . 1. T h e w a t e r s p r a y t e s t w i t h i m p a c t

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 100: Regulations for the Safe Transport of Radioactive Materials

82 ANNEX IV

1-2. 1. 1. Exemptions

Packaging of which the outer layer consists entirely of

metal,wood, ceramic or plastic, or any combination of

those materials.

1-2. 1.2. Method

(a) (i) The sample package, standing on its base on

level ground shall be subjected to a water spray

from each of four directions, as indicated in

(d) below, for a period of 30 min from each

direction, changes of direction being made as

rapidly as possible; or

(ii) The sample package standing on its base on

level ground shall be subjected to a water spray

from all four directions, as indicated in (d)

below, simultaneously and for a period of at

least 30 min;

(b) Without being dried the sample package shall be subĀ­

jected to the 1 .2 m free fall test, as indicated in

1-2. 2. below immediately on removal from the spray

if the procedure indicated in (a) (i) above has been

followed but not until a period of at least li h has

elapsed and not exceeding 2Ā§ h if the procedure indiĀ­

cated in (a) (ii) above has been followed;

(c) The water spray shall be.projected from a nozzle*

operating at 2 Ā± 0. 3 kg /cm 2 conforming to the

following specifications:

(i) The spray shall be in the form of a solid water

cone with an apex angle of 35 degrees measured

at the surface of the nozzle;

(ii) Water consumption shall be 230 Ā± 23 1/h per

spray; and

(iii) Over 50% of the water drops shall be between

3 m m and 5 m m in diameter;

* O n e m eth o d o f fu lf il l in g th e co n d itio n s req u ired in th is te s t is to p rovid e a n o z z le at

th e d isch a rg e end o f w h ich is a f la t n o n -ru sta b le m e ta l p la te , 1 . 6 m m th ic k h av in g 3 6 h o les o f

1 m m d ia m e te r e v e n ly sp aced in c o n c e n tr ic c ir c le s as fo llow s:

1 6 h o les a t 25 m m radius

8 h o le s a t 19 m m radius

8 h o le s a t 13 m m radius

4 h o le s a t 6 m m radius

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 101: Regulations for the Safe Transport of Radioactive Materials

ANNEX IV 8 3

(d) The spray shall be directed downwards onto the

sample from a distance of 2. 4 m (from nozzle to

corner or rim of the package) at an angle of 45 deĀ­

grees to the horizontal and with its axis in the vertiĀ­

cal plane as follows:

(i) For samples of rectangular packages, the vertiĀ­

cal spray plane shall- contain the diagonal

joining the-sprayed corner with the opposite

corner;

(ii) For samples of cylindrical packages standing on

one plane face, the spray shall-be applied from

each of four positions at intervals of 90 degrees.

Water shall drain away as quickly as delivered, i.e. the

package-shall not stand in a pool of water.

1-2 . 2 . T h e f r e e drop test1-2.2. 1. Exemptions

Gas cylinders designed for compressed gas containment

,in excess of 7 kg /cm 2 .

1-2. 2. 2. Method

(a) The sample package shall fall onto the target so as

to suffer maximum damage in respect of the safety

features to be tested;

(b) The height of fall measured from the lowest point

of the sample package to the upper surface of the

target shall be 1 .2 m;

(c) In addition, for fibreboard or 'wood rectangular

packages not exceeding 50 kg in weight, a separate

sample package shall be subjected to a free drop on

each corner of the package from a height of 0. 3 m;

and

(d) In addition for fibreboard cylindrical packages not

exceeding 100 kg in weight, a separate sample package

shall be subjected to a free drop onto each of the

quarters of each rim from a height of 0. 3 m ;

(e) For Fissile Class II packages, the sample package

to be tested under (b) above shall be.subjected, prior

to that test, to a free drop from a height of 0. 3 m

onto each corner, or, in the case of a cylindrical

package, onto each of the quarters of each rim .

1-2.2. 3. Target

The target shall be a rigid, smooth, flat and horizontal

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 102: Regulations for the Safe Transport of Radioactive Materials

8 4 ANNEX IV

1-2 . 3. 1-2. 3. 1.

1-2 . 4. 1-2. 4. 1.

1-2. 4. 2.

1-2. 4. 3.

1-2. 4. 4.

1-3.

1 -3 . 1.

surface. One example of such a target is the upper

surface of a block of material of sufficient mass to absorb

all shocks, when any sample package is dropped upon

it, without appreciable movement. The upper surface

of the block may be covered with a steel plate to protect

that surface.

T he co m p re s s io n test Method

The sample package shall be subjected, for a period of

24 h, to a compressive load equal to the greater of

either five times its own weight, or 1300 kg /m 2 multiĀ­

plied by the vertically projected area of the package.

The load shall be applied uniformly to two opposite sides

of a package, one of which shall be the base on which

the package would normally stand.

T h e p en etra tio n test Method

The sample package shall be placed on a rigid, flat,

horizontal surface which will not move significantly while

the test is carried out.

A bar of 3. 2 cm diameter with an hemispherical end,

weighing 6 kg shall be dropped and directed to fall, with

its longitudinal axis vertical, onto the centre of the

weakest part of the package so that, if it penetrates suffiĀ­

ciently far, it will hit the containment vessel.

The height of fall of the bar measured from its lower

end to the upper surface of the sample package shall be

1 m.

The bar shall be of a material such that it will not signiĀ­

ficantly deform when the test is performed.

P R O C E D U R E S F O R T H E T E S T S R E F E R R E D T O IN

C-2. 2. 2. AJSfD C-2. 2. 3.

E x e m p tio n s f r o m the tes t(a) Type A packagings designed for liquids and satisĀ­

fying the requirements of C-2. 2. 2. (a) or (b) and

(b) Containment vessels of Type A packagings designed

for gases in quantities less than 20 c.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 103: Regulations for the Safe Transport of Radioactive Materials

ANNEX IV 8 5

M e t h o d(a) (i) For Type A packaging designed for liquids the

package shall fall onto the target so as to suffer

the maximum damage in respect of containment;

and

(ii) For Type A packaging designed for gases the

containment vessel shall fall onto the target so

as to suffer the maximum damage in respect of

containment; and

(b) The height of fall measured from the lowest part of

the sample package for (a) (i) above or of the conĀ­

tainment vessel for (a) (ii) above, to the upper surĀ­

face of the target shall be 9 m.

T a r g e t(a) The target shall be a flat, horizontal surface of such

a character that any increase in its resistance to

displacement or deformation upon impact by the

package or containment vessel would not signifiĀ­

cantly increase the damage to the package or conĀ­

tainment vessel.

(b) One example of a target of this type is considered

to be provided by a steel plate at the upper surface

of a block of concrete of mass at least 10 times that

of any sample package that is to be dropped onto it.

The block should be set on firm soil and the steel

plate on its upper surface should be at least 1. 25 cm

thick and wet floated onto the concrete so as to be

in intimate contact with the latter.

P R O C E D U R E S F O R T H E T E S T S R E F E R R E D T O IN

C-2. 3.1., C-5. 3.1 . 1. (b) (i), C-5. 3. 1.2. (b), C-5. 4. 1.2.

(b) (i), C-5. 4 .1 . 3. (b), A N N E X II, II-1 .11 . A N D

A N N E X III, 1-2.1.

The package shall be subjected to the cumulative effects

of the mechanical tests indicated in 1-4. 2. , the termal

test indicated in 1-4. 3. and, unless specifically exempted

therefrom, the immersion test indicated in 1-4. 4 ., in

that order.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 104: Regulations for the Safe Transport of Radioactive Materials

8 6 ANNEX IV

1 -4 . 2 . T h e m e c h a n i c a l t e s t1-4. 2. 1. Packagings exempted from the test

ā–  None

1-4. 2. 2. The test shall consist.of two drops onto a target. The

order in which a sample package is subjected to the two

drops shall be such that on completion of the mechanical

test the sample package will have suffered such damage

as will expose it to the maximum effect in the thermal

test which follows.

1-4. 2. 3. For drop I

(a) The sample package shall fall onto the target so as

to suffer the maximum damage;

(b) The height of fall measured from the lowest point

of the sample package to the upper surface of the

target shall be 9 m;

(c) - The target shall be as defined under 1-3. 3.

1-4. 2. 4. For drop II

(a) The sample package shall fall onto the target so as

to suffer the maximum damage;

(b) The height of fall measured, from the lowest point of

the sample package to the upper surface of the target

shall be 1 m; and

(c) The target shall be the upper end of a solid mild

steel bar of circular section, 15 cm Ā± 0. 5 cm in

diameter. The target surface shall be flat and horiĀ­

zontal with its edges rounded off to a radius of not

more than 6 m m . The bar shall be rigidly mounted

perpendicularly on the foundation described in 1-3.3.

above, and shall be 20 cm long unless a longer bar

would cause greater damage; in that case, a bar of

sufficient length as to cause maximum damage, shall

be used. The characteristics of the mild steel shall

be at least equivalent to those described in Annex II,

1- 2 . 1 .1 -4 . 3. T h e t h e r m a l t e s t1-4. 3. 1. Packagings exempted from this test

None

1-4. 3. 2. Any thermal test shall be considered as satisfactory

provided that the heat input to. the package is no less than

that which would result from exposure of the whole

package to a radiation environment of 800Ā°C for 30 min

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 105: Regulations for the Safe Transport of Radioactive Materials

ANNEX IV 87

with an emissivity coefficient of 0. 9 assuming the surĀ­

faces of the package had an absorption coefficient of 0. 8.

1-4. 3. 3. Method

One method of performing the thermal test which is conĀ­

sidered to satisfy the conditions set down in 1-4. 3. 2. is

described below:

(a) The sample package, at the ambient temperature,

shall be exposed to an open fire meeting the conditions

in sub-paragraph (b) below. The package shall be

supported so that the bottom of the package is 1 m

above the bottom of the tank which will hold the fuel

for the fire. The structure supporting the package

shall be such that it does not prevent direct exposure

of any significant area of the package to the heat

generated. The package shall be positioned so that

maximum damage will result. When an insulation

construction, which is vulnerable to the extent that

it is liable to be partially removed under accident

conditions, is used only 50% of the area of the

packaging shall be protected by that insulation.-

(b) The open fire shall consist of the burning in open

air of a distillate of petroleum with a distillation end

point of 330Ā°C m axim um and a flash point of 46Ā°C

minimum and with a heating value of from 11 lOOkcal^g

to 11 700 kcal/kg. The fire shall be such that all

sides of the package are exposed to a luminous flame

not less than 0 .7 m and not more than 3 m thick.

The tank holding the fuel shall be of such a depth as

to contain the fuel with only nominal freeboard.

(c) The sample package shall be exposed to the fire under

the above conditions for 30 min. It shall not be

cooled artificially until another 3 h have elapsed,

unless it can be demonstrated by the use of athermo-

couple or any other method that the inner temperĀ­

ature has begun to fall.

1 -4 . 4. T h e i m m e r s i o n t e s t1-4. 4. 1. Packages exempted from this test

(a) Packages other than Fissile Class I or II packages;

(b) Fissile Class I or II packages in which optimum

water inleakage was assumed for criticality calcuĀ­

lation purposes.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 106: Regulations for the Safe Transport of Radioactive Materials

8 8 ANNEX IV

1-4. 4. 2. Immersion test procedure

(a) The sample package shall be immersed so that the

joint or joints under test are subjected to a head of

water of at least 0. 9 m . The test time of each joint

shall be 24 h divided by the number of joints to be

tested;

(b) The sample package shall be from 5Ā°C tol5Ā°C warmer

than the water at the commencement of the test.

1-5. T E S T S F O R C O N T A IN M E N T A N D S H IE L D IN G IN T E Ā­

G R IT Y

1 -5 . 1. T h e t e s t f o r i n t e g r i t y o f c o n t a i n m e n t ( c o n t e n t s l e a k a g ei t e s t )

Any commonly accepted leakage test can be employed to

determine that the requirements of 1-1. 4. are met.

1 -5 . 2. T h e t e s t s f o r i n t e g r i t y o f s h i e l d i n g ( r a d i a t i o n l e a k a g et e s t )

1-5. 2. 1. For Type A and Type B packaging, following the tests

under 1-2. above

1-5. 2. 1. 1. With a suitable source in the package the entire surface

of the package shall be examined with X-ray film or an

appropriate instrument to determine that there has been

no significant loss of shielding efficiency.

1-5. 2. 1. 2. No significant loss of shielding efficiency shall mean that

the dose rate at any point on the surface of the package,

when loaded with an iridium-192 source, shall not inĀ­

crease significantly after being subjected to the relevant

tests. If the package is to be used for a particular radioĀ­

nuclide only, that radionuclide may be used as the source

in place of iridium-192.

1-5. 2. 2. For Type B packaging, following the tests under 1-4.

above

1-5. 2. 2. 1. With a suitable source in the package the entire surface

of the package shall be examined with an X-ray film or

an appropriate instrument to determine if there has been

a loss of shielding.

1-5. 2. 2. 2. If there is evidence of loss of shielding at any point on

the surface of the package it must be determined by actual

measurement and calculation, if necessary, that the

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 107: Regulations for the Safe Transport of Radioactive Materials

ANNEX IV 8 9

radiation from the package will satisfy the requirements

of C-2. 3. 1. (b).

P A R T II - TESTS FO R DESIGN O F CAPSU LES FOR

SP EC IA L F O R M RAD IOACTIVE M A T E R IA L

II-1. G E N E R A L

II-1. 1. The sample capsule to be tested shall be constructed as

for transport and the contents of the sample capsule shall

duplicate as closely as practicable the radioactive material

which it is to contain, in particular with regard to the

activities and specific activity.

II-1. 2. A different sample capsule may be used for each of the

tests indicated in II-2. below.

II-1. 3. After each test a leakage assessment shall be performed

by a method no less sensitive than the method given in

II-3. below.

II-2. T E S T M E T H O D S

II- 2 . 1. Im pact testThe sample capsule shall fall onto a target fromaheight

of 9 m . The target shall be a flat, horizontal surface

of such a character that any increase in its resistance

to displacement or deformation upon impact by the capsule

would not significantly increase the damage to the capsule.

I I - 2. 2. P e r c u s s i o n t e s tThe sample capsule shall be placed on a sheet of lead

which is supported by a smooth solid surface and struck

by the flat face of a steel billet so as to produce an imĀ­

pact equivalent to that resulting from the free fall of

1. 4 kg through 1 m . The flat face of the billet shall be

2. 5 cm in diameter with the edges rounded off to a radius

of not less than 3 m m . The lead, of hardness number

3. 5 to 4. 5 on the Vickers scale and not more than 25m m

thick, shall cover an area greater than that covered by

the capsule. A fresh surface of lead shall be used for

each impact.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 108: Regulations for the Safe Transport of Radioactive Materials

ANNEX IV

H eating testThe sample capsule shall be heated in air to a temperĀ­

ature of 800Ā°C and held at that temperature for a period

of 10 min and then shall be allowed to cool.

Im m e rs io n testThe sample capsule shall be immersed for 24 h in water

at room temperature. The water shall be at pH 6- pH 8,

with a maximum conductivity of 10 iuip/cm.

L E A K A G E ASSESSM ENT M E T H O D

Step 1Immerse the sample capsule in a solution which will not

attack the material of which the sample capsule is made

and which, under the conditions of this method, has been

demonstrated to be effective in removing the radioisotope

involved. Heat the solution to 50Ā°C Ā± 5Ā°C and hold it at

this temperature for 8 h.

Step 2

Store the sample capsule for at least 7 d and repeat step 1.

If the total activity in each solution is less than 0. 05 /jc,

the sample capsule shall be considered to be leak-free.

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 109: Regulations for the Safe Transport of Radioactive Materials

A N N E X V

S P E C I F I C A T I O N S O F P A C K A G I N G S F O R N O N - F I S S I L E M A T E R I A L S

The Agency invites the submission of packaging designs

which, when recognized as meeting the relevant proĀ­

visions of these regulations, will be described or reĀ­

ferred to under this heading.

91

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 110: Regulations for the Safe Transport of Radioactive Materials

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 111: Regulations for the Safe Transport of Radioactive Materials

L I S T O F P A R T I C I P A N T S O F P A N E L S

A N D O T H E R M E E T I N G S

G EN ER A L REVISIO N O F REG ULATIO NS FOR TH E S A F E TRANSPO RT O F RAD IO A CTIVE M A TER IA LS

P A N E L M E E T IN G

L ist o f participa nts at the m eetin gs h eld at the International A tom ic E n e rg y A gen cy H ea d q u a rters, Vienna, 1 1 -2 2 M arch 1963 :

Chairm an

Andre, G .E . Union Miniere du Haut-Katanga,

Belgium

P anel m e m b e rs

Capet, H.

assisted by

Blum, M . , Duvaux, Y. ,

Jacquemin, Y.

Dmitric, V.

Gibson, R.

assisted by

Aspinall, K. J. , Fairbairn, A.

Armstrong, J.

Iansiti, E .

assisted by

Crostini, R.

Leshchinsky, N.

Commissariat a l'energie

atomique, France

Federal Nuclear Energy

Commission, Yugoslavia

United Kingdom Atomic Energy

Authority

Ministry of Transport,

United Kingdom of Great Britain

and Northern Ireland

Comitato Nazionale per l'Energia

Nucleare, Italy

State Committee on Utilization

of Atomic Energy,

Union of Soviet Socialist Republics

9 3

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 112: Regulations for the Safe Transport of Radioactive Materials

9 4 LIST OF PARTICIPANTS

Nishiwaki, Y.

Rogers, L . R.

assisted by-

Barker, R. F . , Patterson, E . ,

George, T.

Subrahmaniam, G.

Wahlberg, T.

Wilson, A . R.

R ep resen ta tiv es o f O rganizations

Verhey, J. H.

Belser, W . E .

Darioli, P.

Calcagno, G.

Zach, V.

Scalliet, R.

Tonzig, G.

Asyee, J.

University of Engineering, Tokyo,

Japan

United States Atomic Energy

Commission

Bureau of Explosives,

United States of America

Atomic Energy Establishment,

Trombay, India

A. B . Atomenergie, Sweden

Australian Atomic Energy

Commission

Central Commission for the

Navigation of the Rhine

Centre d'etudes du risque

atomique, Comite europeen des

assurances

Central Office of International

Railways Transport

Committee of the Organization

for Collaboration of Railways

European Atomic Energy

Community

European Company for the

Chemical Processing of IrradiĀ­

ated Fuel

Selby, R. A. European Nuclear Energy Agency

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 113: Regulations for the Safe Transport of Radioactive Materials

Dente, L . G.

Groenewege,

Lecomte, P . .

Detiers, N.

Hellen, E .

Swaton, W . F,

Van Es, K. J.

Domanus, J. .

Musialowicz,

Breton, P . G.

Masson, F.

Koster, L .

Devik, F.

Intergovernmental Maritime

Consultative Organization

A . , International Air Transport

A. Association

International Civil Aviation

Organization

International Labour Organisation

,, International Road Transport

Union

International Standards Organi-

T . zation

International Union of Marine

Insurance

United Nations (Economic

Commission for Europe)

Universal Postal Union

World Health Organization

LIST OF PARTICPANTS 95

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 114: Regulations for the Safe Transport of Radioactive Materials

9 6 LIST OF PARTICIPANTS

C O N S U LT A N T S ' M E E T IN G

L ist o f participants at the m eetin gs h eld at the International A tom ic E n e rg y A gen cy H ead qua rters, Vienna, 2-13 D e c e m b e r 1963 :

Chairm an

Van Lokhorst, C .S .

M em b ers

Capet, H.

assisted by

Sousselier, Y . , Bouillet, J . ,

Charamathieu, A. , Moreau, J.

Leshchinsky, N.

Gibson, R.

assisted by

Fairbairn, A . , Daniels, J. T . ,

Morley, F.

Armstrong, J.

Iansiti, E .

assisted by

Zambrini, R . , Crostini, R.

Rogers, L.

assisted by

Paxton, D . H . ,

Patterson, D. E . , Barker, R.J.,

George, T.

Afdeling Gevaarlijke Stoffen,

Netherlands

Commissariat a l'energie

atomique, France

State Committee on Utilization

of Atomic Energy,

Union of Soviet Socialist Republics

United Kingdom Atomic Energy

Authority

Ministry of Transport,

United Kingdom of Great Britain

and Northern Ireland

Comitato Nazionale per l'Energia

Nucleare, Italy

United States Atomic Energy

Commission

Bureau of Explosives,

United States of America

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 115: Regulations for the Safe Transport of Radioactive Materials

LIST OF PARTICIPANTS 9 7

Rotnicki, J.

assisted by

Musialowicz, T .

Wilson, A . R.

O b serv er

Kolb, W .

R ep resen ta tiv es o f O rganizations

Calcagno, G.

Zach, V.

Tonzig, G . ,

Trousson, N.

Aysee, J.

Selby, R. A. ,

Marcus, F. R.

MacAngus, J. L.

Lecomte, P. A.

Domanus, J.

Central Radiological Protection

Laboratories, Poland

/Australian Atomic Energy

Commission

Physikalisch- Technische

Bundesanstalt,

Federal Republic of Germany

Central Office of International

Railways Transport

Committee of the Organization

for Collaboration of Railways

European Atomic Energy

Community

European Company for the

Chemical Processing of

Irradiated Fuel

European Nuclear Energy

Agency

Intergovernmental Maritime

Consultative Organization

International Air Transport

Association

International Standards

Organization

Rahi, M. Universal Postal Union

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 116: Regulations for the Safe Transport of Radioactive Materials

98 LIST OF PARTICIPANTS

D R A F T IN G C O M M IT T E E 8-10 JA N U A R Y 1964

BouiUet, J.

Gibson, R.

Commissariat a l'energie

atomique, France

United Kingdom Atomic Energy

Authority

D R A F T IN G C O M M IT T E E 19-30 O C T O B E R 1964

C hairm an

Gibson, R.

C om m ittee M em b ers

Barker, R. E .

Bouillet, J.

Leshchinsky, N.

O b serv er

United Kingdom Atomic Energy

Authority

United States Atomic Energy

Commission

Commissariat a l'energie

atomique, France

State Committee on Utilization

of Atomic Energy,

Union of Soviet Socialist

Republics

Van Lokhorst, C. S. Afdeling Gevaarlijke Stoffen,

Netherlands

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 117: Regulations for the Safe Transport of Radioactive Materials

R EVISIO N O F S P E C IA L IZ E D S U B JE C T S

LIST OF PARTICIPANTS 99

M E E T IN G O F C O N S U LT A N T S F O R T H E REVISION O F

PROVISIONS O N T H E T R A N SP O R T O F FISSILE M A T E R IA LS

L ist o f p a rticip a n ts at the m eetin g s h eld at the International A tom ic E n e rg y A gen cy H ea d qu a rters, Vienna, 2 6 -3 0 M arch and

26 S ep tem b er - 3 O ctober 1962 :

Breton, D . Commissariat a l'energie

M E E T IN G O F CO N SU LT A N TS O N PACKAG IN G TESTS

L ist o f participants at the m eetin gs h eld at the International A tom ic E n erg y A gency H eadquarters, Vienna, 2 1 -2 5 O ctober 1963:

Chairm an

atomique, France

Paxton, H. C. Los Alamos Scientific Laboratory,

United States of America

Woodcock, E .R . Health and Safety Branch,

United Kingdom Atomic Energy

Authority

ā€¢Fairbairn, A. United Kingdom Atomic Energy

Authority

M em b ers

Capet, H.

assisted by

Vinarnick, L.

Commissariat a l'energie

atomique, France

Domanus, J. International Standards OrganiĀ­

zation

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 118: Regulations for the Safe Transport of Radioactive Materials

George, T.

assisted by

Barker, R. F.

1 0 0

Grange, A.

Bureau of Explosives,

United States of America

United States Atomic Energy

Commission

United Kingdom Atomic Energy

Authority

LIST OF PARTICIPANTS

Iansiti, E . Comitato Nazionale perl'Energia

Nucleare, Italy

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 119: Regulations for the Safe Transport of Radioactive Materials

LIST OF PARTICIPANTS 10 1

L ist o f participants at the m eetin gs h eld at the International A tom ic E n erg y A gency H ea dqua rters, Vienna, 17-21 F eb ru a ry 1964:

P A N E L S ON T H E D ESIG N AND T E S T IN G O F PACKAG IN G

Chairm an

Fairbairn, A.

P anel m e m b e rs

Capet, H.

assisted by

Remy, J.

Domanus, J.

United Kingdom Atomic Energy

Authority

Commissariat a l'energie

atomique, France

International Standards OrganiĀ­

zation

George, T.

assisted by

Barker, R. F.

Bureau of Explosives

United States of America

United States Atomic Energy

Commission

Grange, A.

Iansiti, E.

Veith, H.

assisted by

Neider, R . , Kolb, W .

Wilson, A. R.

United Kingdom Atomic Energy

Authority

Comitato Nazionale perl'Energia

Nucleare, Italy

BundesanStalt fiir Material-

priifung,

Federal Republic of Germany

Physikalisch- Technische

Bundesanstalt

Federal Republic of Germany

Australian Atomic Energy

Commission

Isaev, B. M . USSR Permanent Mission

Vienna

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 120: Regulations for the Safe Transport of Radioactive Materials

O b serv ers

1 0 2 LIST OF PARTICIPANTS

Asyee, J. European Company for the

Chemical Processing of

Irradiated Fuel

Van Lokhorst, C. S. Afdeling Gevaarlijke Stoffen,

Netherlands

L ist o f participants at the m eetin gs h eld at the International A tom ic E n e rg y A gency H ea d qu a rters , Vienna, 25 May - 5 Ju n e 1964 :

C hairm an

Capet, H.

P anel m e m b e rs

Crostini, R.

Domanus, J.

George, T.

assisted by

Barker, R. F.

Commissariat a l'energie

atomique, France

Comitato Nazionale per l'Energia

Nucleare,

Italy

International Standards

Organization

Bureau of Explosives,

United States of America

United States Atomic Energy

Commission

Grange, A.

assisted by

Fairbairn, A.

Remy, J.

assisted by

Chappelier, N.

United Kingdom Atomic Energy

Authority

Commissariat a l'energie

atomique, France

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 121: Regulations for the Safe Transport of Radioactive Materials

LIST OF PARTICIPANTS 1 0 3

Veith, H.

assisted by-

Kolb, W .

Wilson, A. R.

Bundesanstalt fur Material-

priifung,

Federal Republic of Germany

Physikalisch- Technische

Bundesanstalt,

Federal Republic of Germany

Australian Atomic Energy

Commission

O b serv ers

Asyee, J.

Wredberg, L . O.

Jonasson, G.

Mac Angus, J. L.

MacDonald, L. R.

European Company for the

Chemical Processing of

Irradiated Fuel

A. B . Atomenergie, Sweden

Intergovernmental Maritime

Consultative Organization

Atomic Energy of Canada

Limited

Martin, W . A. Board of Transport

Commissioners for Canada

Scalliet, R. ,

Trousson, M .

European Atomic Energy

Community

Van Lokhorst, C. S. Afdeling Gevaarlijke Stoffen,

Netherlands

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 122: Regulations for the Safe Transport of Radioactive Materials

1 0 4 LIST OF PARTICIPANTS

S E C R E T A R IA T

S cien tific S e c re t a r ie s

Appleton, G . Division of Health, Safety and

Servant, J. Waste Disposal, IA EA

E d ito r

Doyle, E. Division of Scientific and

Technical Information, IA EA

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 123: Regulations for the Safe Transport of Radioactive Materials

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 124: Regulations for the Safe Transport of Radioactive Materials

IAEA SALES AGENTS

Orders for A gen cy p u b lica tio n s can be p laced with your b o o k selle r or any of our s a le s ag en ts lis te d below :

A U S T R A L I AHunter P u b lic a tio n s ,2 3 M cK illop S treet M elbourne, C . l

A U S T R I AG eorg Fromme & Co.Sp en gergasse 39 V ienn a V

B E L G IU MO ffic e in tern ational de lib ra ir ie 30 , avenue Marnix B r u s s e ls 5

B R A Z I LL iv raria K osm os E d itors Rua do R o sa rio , 1 3 5 -1 3 7 R io de Ja n eiroA gen cia E xp oen te O sca r M. S ilv a Rua X a v ier de T o led o , 1 4 0 - 1Ā° Andar (C aix a P o s ta l No. 5 .6 1 4 )S3o P au lo

BYELO RU SSIA N SO V IE T SO C IA L IST R E P U B L IC Se e under USSR

C A N A D AT h e Q u een 's P rin ter O ttaw a, O ntario

C H I N A (T aiw an)B o o k s and S c ie n t if ic Su p p lies S e rv ic e , L td .,P .O . B o x 83T a ip e i

D E N M A R KE jn a r Munksgaard L td .6 Norregade C openhagen K

F I N L A N DA kateem inen K irjakauppa K esku skatu 2 H elsin k i

F R A N C EO ffic e in tern ation al de docum entation e t lib rairie 4 8 , rue G a y -L u ssa c P a r is 5e

G E R M A N Y , F e d e ra l R ep u b lic of R . Oldenbourg R osenheim er S tra sse 145 8 Munich 8

I S R A E LH eiliger and C o.3 Nathan S tra u ss S treet Jeru salem

I T A L YA gen zia E d ito ria le In tem azion ale O rganizzazioni U n iv ersa l! (A .E .I .O .U .) V ia M eravigli 16 Milan

J A P A NMaruzen Company Ltd .6 , T ori Nichome N ihonbashi (P .O . B o x 6 0 5 )Tokyo C entral

M E X I C OL ib raria In tem acio n al Av. Sonora 206 M exico 11 , D .F .

N E T H E R L A N D S N .V . M artinus N ijh off L an g e Voorhout 9 T h e Hague

N EW Z E A L A N DWhitcombe & Tom bs, L td .G .P .O . B ox 1894 W ellington, C . l

N O R W A YJohan GrundtTanum K arl Jo h a n s g ate 43 O slo

P A K I S T A NK arach i E d u cation S o c ie ty Haroon Chambers South N apier Road (P .O . B o x No. 4866)K arach i, 2

P O L A N DO srodek R ozpow szechn iana Wydawnictw Naukowych P o ls k a A kadem ia Nauk P a fa c Kultury i Nauki Warsaw

S O U T H A F R I C AVan S c h a ik 's B ook store (P ty ) L td . L ib ri B u ild ing Church S treet (P .O . B o x 724)P re to r ia

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 125: Regulations for the Safe Transport of Radioactive Materials

S P A I NL ib re ria B o sc hRonda de la U niversid ad 11B arcelo n a

S W E D E NC .E . F r itz e s Kungl. Hovbokhandel F red sg atan 2 Stockholm 16

S W I T Z E R L A N D L ib ra ir ie P ay o t Rue G renus 6 1211 G eneva 11

T U R K E YL ib ra ir ie H achette 4 6 9 , Is tik ld l C addesi B ey og lu , Istanbu l

UKRAINIAN SO V IE T SO C IA L IST R E P U B L IC See under USSR

UNION O F SO V IE T SO C IA L IST R E P U B L IC S Mezhdunarodnaya Kniga Sm olen skaya-Sennaya 32-34 Moscow G -200

U N ITED KINGDOM O F G R E A T BR ITA INAND NORTH ERN IRELAN D

Her M a je s ty 's Station ery O ffice P .O . B o x 569 London, S .E . l

U N ITED S T A T E S O F AMERICA N ation al A gency for In ternation al P u b lic a tio n s , In c .3 17 E a s t 34th S treet New Y ork, N .Y . 10016

V E N E Z U E L ASr. B rau lio G ab riel C h acares Gobem ador a C an d ilito 37 San ta R o s a lia (Apartado P o s ta l 8092)C a ra c a s D .F .

. Y U G O S L A V I AJu go slo v en ska K njiga T e r a z ije 27 B elg rad e

IAEA p u b lica tio n s can a lso be purchased re ta il a t the United N ation s Bookshop a t U nited N ations H eadquarters, New York, at the new s-stand at the A gen cy 's H eadquarters, V ienn a, and a t m ost co n feren ces , sym posia and sem inars organized by the A gency.

In order to fa c i l i ta te the d istribution of i t s p u b lica tio n s, the Agency i s prepared to a c c e p t payment in UNESCO coupons or in lo ca l cu rren cies .

O rders and in qu iries from cou ntries where s a le s ag en ts have not y et been appointed may be se n t t o :

D istribution and S a le s U nit, International Atomic Energy Agency, Karntner R ing 11, Vienna I , A ustria

This publication is no longer valid Please see http://www-ns.iaea.org/standards

Page 126: Regulations for the Safe Transport of Radioactive Materials

I N T E R N A T I O N A L A T O M I C E N E R G Y A G E N C Y V I E N N A , 1965

PRICE: U S A a n d C a n a d a : U S $ 2 . 5 0A u s t r i a a n d e l s e w he re : S 52 , 5 0 (15 / - stg ; F.Fr. 10,-; D M 8,-)

#

i

I

i"i>

J

fr>\

i}\f

yif

\I

i

This publication is no longer valid Please see http://www-ns.iaea.org/standards