JAERI1 -Tech JP0250564

2002-083

STUDY FOR REDUCING RADIOACTIVE SOLID WASTE ATITER DECOMMISSIONING PERIOD

Shinichi SATO*, Masanori ARAKI, Junji OHMORI, samnu OHNO

Satoshi SATO, NMichinori YAMAUJCI-I and Takeo NISHITAN1

Japan Atomic Energy Research Institute

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Information Division, Department of Intellectual Resources, Japan Atomic Energy

Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken T319i1l95, Japan.

© Japan Atomic Energy Research Institute, 2002

JAERI-Tech 2002 -083

Study for Reducing Radioactive Solid Waste at ITERDecommissioning Period

Shinichi SATO*, Masanori ARAKI, Juniji OH-MORI, Isamu OHNO,

Satoshi SATO+, Michinori YAMAUCHI+ and Takeo NISITANI+

Department of ITER Project

Naka Fusion Research Establishment

Japan Atomic Energy Research Institute

Naka-machi, Naka-gun, Ibaraki-ken

(Received September 4, 2002)

It is one of the foremost goals for ITER to demonstrate the attractiveness with regard to

safety and environmental potential. This implies that the radioactive materials and waste

at decommissioning phase should carefully be treated with prescribed regulations.

As possible activities during the Coordinated Technical Activity (CIA), the authors have

performed a feasibility study for searching the possibility of effective reduction in the

activated level as reasonably achievable as possible by taking account of minimum material

changes while keeping original design concept and structure. Major induced aivation in

ITER comes from activated nickel and cobalt so that it is effective for the major structural

components to minimize their material contents. Employing less Ni and Co steel in place

of high-Ni austenitic stainless steel for blanket shield block, vacuum vessel shield material

and TF coil casing has been considered as one of the effective plans to reduce the activated

materials at the decommissioning phase. In this study, two less-Ni austenitic stainless

steels are evaluated; one is high-Mn austenitic stainless steel JK2 which is developing for

jacket material of ITER CS coil and the other is S204L/ASTM-XM- 1 1 which is also high-Mn

steel specified in the popular standards such as American Society of Testing and Material

(ASTM).

*:current address; Kawasaki Heavy Industry Co. Ltd.

+: Departmnent of Fusion Engineering Research

JAERI-Tech 2002-083

Based on the material changes, activation analyses have been performed to investigate the

possibility of reducing radioactive wastes. As a most impressive result, at 40 years after the

termination some of main components such as a TF coil casing will reach to the clearance

level which is specified by IAEA, and most components will be categorized into extremely

low level waste except for limited components. These results will give the appropriate short

decommissioning period that is assumed to start at 100 years after the termination in the

original design.

Keywords: ITER, Decommissioning, Radwaste, Clearance, High-Mn Steel, Activation Level

JAFRI-Tech 2002 -083

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JAERI-Tech 2002-083

Contents

I. Introduction..................... 1

2. Activation Analysis..................... 2

2.1 Analysis Condition..................... 2

2.2 Analysis Results..................... 5

3. Clearance Potential of Components. ............... 20

3.1 Clearance Level..................... 20

3.2 Clearance Indices.....................21

4. Activation Level of Radwaste.................30

4.1 Classification of Radwaste.................30

4.2 Categorization of Radwaste.................30

5. Preliminary Estimation of the Amount of Radioactive Wastes .... 41

6. Conclusions..................... 43

Acknowledgements.....................44

References..................... 44

Appendix - 1.....................45

Appendix - 2.....................59

Appendix - 3..................... 73

Appendix- 4.....................77

JAERI-Tech 2002-083

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JAERI-Tech 2002-083

1. Introduction

It is one of the foremost goals for ITER to demonstrate the attractiveness with

regard to safety and environmental potential. This implies that the radioactive

materials and waste at decommissioning phase should be carefully treated with

prescribed regulations. The benefit in the safety and environmental impact of

fusion has been highly noticed. The rad-waste issue is, however, sometimes taken

seriously. In particular, for public environments it is very important to demonstrate

production of less activated wastes for emphasizing the attractiveness of fusion,

especially in ITER.

In the series of 2001 ITER Final Design Report (FDR) documents, activation level

and its weight are roughly estimated. In ITER Generic Site Safety Report (GSSR) [1],

some of large components such as Toroidal Field (TF)/Poloidal Field (PF) coils are

categorized into low level activated components that are close to clearance level

except for conductor at 30 years after shutdown. As possible activities during the

Coordinated Technical Activity (CTA), it is worth performing a feasibility study for

searching the possibility of more reduction in the activated level by taking account of

minimum material changes while keeping original design concept and structure.

Based on it, reassessment of the activation level and the amount of radwaste

volumes will give us positive aspects for public acceptance. Final goal for this

study is to reduce not only the activation level to around one tenth of the current

value but also the amount of radioactive wastes whose radiation level exceeds the

clearance level. In this study ITER decommissioning is assumed to start at 30 - 40

years after final shutdown.

Employing less nickel and cobalt steel in place of high nickel austenitic stainless

steel for blanket shield block, vacuum vessel shield material and TF coil casing has

been considered as one of the effective plans to reduce the activated materials at the

decommissioning phase. It is noted that for application of their materials it is

necessary to provide further evaluations such as the material applicability,

fabricability, compatibility with the related components and acquisition. In

particular the fabricability for magnet structure, the weldability is the most

important issue so that R&D study is intensively ongoing as a part of demonstration

of fabricability for ITER CS jacket material.

In this study, activation analysis including the geometry of major ITER

components is described in section 2 and its results are presented in section 3 and 4.

Based on the assessment, radwaste masses in both cases are briefly estimated and

compared in section 5.

JAERI-Tech 2002-083

2. Activation Analysis

2.1 Analysis Condition

A cross sectional view of ITER tokamak components is shown in Fig.2.1-1.

Configuration of TF coil, vacuum vessel and blanket modules are also shown in Figs.

2.1-2 to 2.1-4. In accordance with the configurations, one-dimensional model is

made for the activation analysis. Basic flow of the activation analysis studied in

this report is shown in Fig.2.1-5. Detailed analysis conditions are shown in the

following sections.

2.1.1 Analysis Case

Activation analyses have been performed to investigate the possibility of reducing

radwaste due to the changes of component materials. Materials combinations in

this analysis are shown in Table2.1-1. Two analysis cases are considered; one is

'High-Ni steel case' of the current design base, the other is 'ligh-Mn steel case'

based on the proposal for reducing the activation level. In the High-Mn case,

materials of blanket shield block, vacuum vessel shield material and TF coil casing

were changed to high-Mn/less-Ni steels. To capture thermal neutron which is

generated through the shielding materials from 14 MeV , boron content in shielding

materials of blanket and vacuum vessel was increased to 4 wt%. In the current

design of vacuum vessel, SS 304 with 2 wt% boron contents is selected as the shield

material except for ferromagnetic (SS430) insert regions (under TF coil in the

outboard area) for reducing toroidal field ripple loss.

2.1.2 Analysis Model

One-dimensional annulus models for inboard and outboard regions were applied

to this analysis both for neutron transport and activation analysis. Radial build-up

of the ITER tokamak components is shown in Fig.2.1-6. Detailed analysis models

for inboard and outboard region are also shown in Fig.2.1-7 and Fig.2.1-8,

respectively. Radial thickness of major components related to the activation

products is listed below;

1) Blanket Module:

8lmm(separable first wall) + 369mm(shielding block)

2) Vacuum Vessel:

Inboard mid-plane:

6Omm(inner shell) + 217mm(shield material) + 6Omm(outer shell)

Outboard mid-plane:

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6Omm(inner shell) + 630mm(shield material) + 6Omm(outer shell)

3) TF Coil:

Inboard mid-plane:

75mm(plasma-side casing) + 576mm(winding pack) + 225mm(nose region)

Outboard mid-plane:

124mm(plasma-side casing) + 633mm(winding pack) + 124mm(cryostat-

side casing)

Some regions in the functional materials such as shielding blocks for blanket and

vacuum vessel are modeled as a homogeneous layer.

2.1.3 Chemical Composition of Material

In TER-GSSR, induced activity of main tokamak components at 30 years after

final shutdown is dominated by 'Co and 63Ni. These radionuclides are mainly

produced by the following reactions with thermal and fast neutrons;

For ' 0Co : 5 Co (n, y)60Co, 60Ni (nf,,,, p )60C o

For 6 %N 62Ni (n, y) 63 Ni, 6 CU (nfas, p )6 Ni

In the current design, austenitic stainless steel with high nickel contents is

selected for the main structure of tokamak components. Cobalt around 0.01 to 0.05

weight percent is contained in nickel ore as an impurity. Therefore, if austenitic

steel with low nickel and cobalt contents were used for their components, it would

be expected that activation products of 6 N and 6 Co drastically be decreased,

resulting in lower activation level and smaller amount of radioactive wastes at the

decommissioning phase for an appropriate period. It is also important to add

boron into cooling water or neutron-shield blocks of blanket and vacuum vessel to

reduce the amount of thermal neutrons. Therefore, idea for material changes is to

play roles of reducing the radioactive wastes and its radiation level for TF coil casing

and of reducing activation levels for the shield blocks.

Chemical compositions of materials in this analysis are summarized in Table2.1-2.

For High-Ni steel case (current design), a modified SS316L(N) steel (S EK1) which

contains high nitrogen to achieve high strength is employed as the structural

material of TF coil casing. For the blanket sideld block and vacuum vessel shell,

SS316L(N)-ITER grade with low cobalt(<0.05wt%/) and boron (<0.Olwt%) is used.

Type 304 stainless steel with 2wt%/ boron contents is used for the shield material of

the vacuum vessel.

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JAERI-Tech 2002-083

For High-Mn steel case, JK2 that is containing manganese instead of nickel is one

of the candidate materials for TF coil casing. This material has been developed

during ITER Engineering Design Activities (EDA) and its mechanical properties

meet with the following requirements.

For Chemical Composition of Material,Niobium (Nb) content < 0.01 wt%Nickel (Ni) content < 5.0 wt/oMolybdenum (Mo) content < 0.5 wt%(Cobalt (Co) content not specified)

For Mechanical Strengths of Material at Cryogenic Temperature,Yield Strength (Sy) > 1000 MPaFracture Toughness (KIC) > 200 MPa m' /2

ITER project has specified each of material compositions. However, for TF coil

casing there is no specification on cobalt contents. Since cobalt is one of the impact

radionuclides for the induced activity, these contents should be reduced as low as

possible at the decommissioning point of view. In this study, cobalt content in

high-Mn steel is assumed to be -0.01 wt% for the following reason; in general, cobalt

is naturally included in Ni ore as an impurity element and reducing Ni in steel

decreases proportionally. In high-Ni steel such as SS 316L(N) ITER-grade (Ni

content: 12-14 wt%) cobalt content is specified to be less than 0.05 wt%. Therefore,

cobalt contents for JK2 and other high-Mn steels (Ni content: <5.0 wt%) can be

expected to be less than 0.02 wt%/ in proportion to Ni contents. It believes that

further control will be possible for reducing its content to 0.01 wt%.

For the shield material of vacuum vessel, SS204L with 4w% boron or relevant

material with low Ni contents (< wt%) will be candidate. Nickel contents in JK2

and S5204L are 4.92 wt% and 5wt%, respectively. For JK2 steel molybdenum

content of 0.5wt%/ is applied to this analysis. Technetium-99 (Tc, half life: 2.13x10'

years) is predominantly generated by 98Mo(n, y99 Mo(pV)99Tc reaction with neutron.

Type SS 316L(N) ITER-grade (S316L(N)-IG) has higher Mo content (2.5 wt%) than

JK2 (0.5 wt%), easily expecting larger activation by 9 Tc in High-Ni case. Niobium

content in the structural material is assumed to be 0.Olwt% in both materials.

SS316L(N)-IG with low cobalt (<0.05 wt%) and boron (<0.01 wt%) is used for the

vacuum vessel shell.

2.1.4 Operation Scenario

For the assessed operation scenario in this activation analysis, 'M-DRG-1' specified

in ITER-GSSR was adopted. Typical condition of the operation scenario is shown

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JAERI-Tech 2002-083

as follows;

1) Operation period:

20 years + 12 days (the first half 10 years + 6 days, the second half 10 years + 6

days)

2) Neutron wall load on FW surface: 0.56 MWM-2 (average)

3) Neutron fluence on FW surface: 0.304 MWa. M 2 (average)

4) Maximum duty cycle for operation: 0.25

5) Assumption of special operation campaign: two 6 days campaigns at 25% duty

cycle at the end of the first and second decades of operation

6) Neutron Fluence build-up :see below

- Neutron Fluence build-up in the first 10 years _______

Years 1-4 5 6 7 8 9 10 Total0.022+I

Neutron Fluence, (MWa M) 0 0.006 0.008 0.012 0.020 0.024 0.0940.002*

- The second 10 years

Years 11-20 Total

2 ~~~~~~~~~~~~0.208+1Neutron Fluence, (MWa~ -M) 0.2100.002* J_ _ _ _

Note) *:Neutron fluence for 6 days campaign with 25% duty cycle

2.1.5 Neutron Flux Distribution

The one dimensional discrete ordinate code ANISIN was used for neutron and

gamma ray transport analysis. The nuclear data was based on FUSION-40. Figure

2.1-9 shows neutron fluxes in the inboard and outboard areas during normal

operation.

2.1.6 Activation Analysis

System code THIDA [2] is applied to the activation analysis. For assessment of

the induced activities from the inside (CS coil) to the outside (TF coil) regions, 21

calculation points are selected as shown in Fig.2.1-10. Basically induced activity of

each component in front and rear surfaces is evaluated.

2.2 Analysis Results

Total pecific activities in the major components are summarized in Table2.2-1.

At the final shutdown the maximum specific activity of 2.92 TBq/cc will be

produced in the blanket shielding material. During cooling period of 30 years, the

specific activity decays more than four orders of magnitude. Figures 2.2-1 to 2.2-4

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JAERI-Tech 2002-083

show relationships between specific activity and decay time after final shutdown for

the inboard components (blanket shield, vacuum vessel shell and TF coil case). Up to

30 years after final shutdown, dominant isotopes that mostly contribute to the

specific activities are as follows;

[For blanket shield]

`5Fe (half life: 2.7 y), H (1 2.3 y), 3 Ni (100.1y), 60Co (5.3y)

[For vacuum vessel]

15 Fe (half life: 2.7 y), 63Ni (100.1y), 'Co (5.3y)

[For TF coil casing]

`5Fe (half life: 2.7 y), H (12.3 y), 63 Ni (100.1y), `0Co (5.3y)

Major neutron reactions for these radioisotopes with regard to activation are

described as follows;5 8Ni(n, np)57Co -*>EC, 0.837MeV (57 Fe, stable)5 4 Fe(i,p)'Mn, 55Mn(ni, 2n)5 Mn --*EC, 1.377MeV (5 4Cr, stable)5 0Cr(n,2n)49 Cr -->f3&EC, 2.628MeV (V, active)49V --*EC, 0.602MeV (49 Tri, stable)54Fe(n, 'y)55Fe, 'Fe(n,2n) 55 Fe , 5 8Ni(n, (x)5 Fe --)EC, 0.2313MeV (Mn, stable)60Ni(n, p)'Co -*1-&,y, 2.824MeV (60Ni, stable)62 Ni(n, y)6 3Ni -1,0.0659MeV (63CU, stable)58Ni(n, y)59Ni -)>EC, 1.073MeV (59Co, stable)

It is noted that radioactive isotopes ` 5Fe and 60Co decay rather fast compared with

the other radioactive components.

Beyond about 100 years, more longer-lived isotopes, 14C (half life: 5.7x 10' y), 9Ni

(7.5x104y), 14Nb (2.0x 10 4 y), 9 Mlo (3.5x10' y) etc. dominate the specific activities. Specific

activities (vs. decay time after final shutdown) of transmutation products in the major

components are attached to Appendix-I1.

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JAERI-Tech 2002-083

Table2.1-1 Material combinations for activation calculations

Component Current Design This Study

(High-Ni case) (Less-Ni/High-Mn case)

Blanket First wall Be + Cu + SS316LN-IG [Il

Blanket Shield SS3 16LN-1G[* 1 K2 *5 with 4%Boron

Vacuum Vessel Shells SS3I161NAlG[*21

Shield Materials SS30467 with 2%Boron [*3] SS204L-[*6] with 4%Boron

between VV Shells

TF Coil Case SS EKI1 [*41 JK2 [*5]

----NOTES --[*1] Type 316 L(N) austenitic stainless steel (ITER-gradel), Low cobalt (<0.05wt%)[*2] :Type 316 L(N) austenitic stainless steel (ITER-grade2), Low cobalt and boron

(Co:<0.05wt%, B:<0.00]IOwt%),Nb content: <0.0 I wt%

[*3] Borated stainless steel (for example, ASTM A 887-89), Low cobalt (<0.05wt%)[*4] European Kind number (EKI) is a modified SS316L(N) steel which uses high

nitrogen to achieve high strength.[*5] Japanese Kobe number 2 (JK2) is a nitrogen-strengthened, high Mn austenitic

stainless steel.[*61 SS204L is a high Mn austenitic stainless steel specified in ASTMW-XM-1 .

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JAERI-Tech 2002-083

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JAERI-Tech 2002-083

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JAERI-Tech 2002-083

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- 12 -

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JAERI-Tech 2002-083

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JAERI-Tech 2002-083

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.51 a3 *---0i-*-*~---- *

1 04~~~~~~:

1 0 2~ ~ ~ ~~~ 1 0 1 07 1 8 091. - In

Time after final shutdown (sec)

Fig.2.2 Specific activities of inboard Vashe (iell)

- 18 - ~ ~ ~ -X - (-1

JAERJ-Tech 2002-083

--X- -c-14--A--Co-57

___________T____ _ _T _______ __ _______ - -W--Co-58

U,~~~~~~~~~~~~ -- Co 60

o 3 _ _ _ _ _ _ ~ ~ ~ ~ ~ ~ - A - H

10 ........................................... )E - n 5

U~~~~~~~~~~~d o9)1)~~~~~~~~~~~~~~~b9

a. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ -1-N-3

4~~~~~~~~~~~~~~~~~1b91 I .......................... .. . ... .........- P 1

-~~~~-*~~~~~- -- G Ni6-- --- 10Tc9

.5

AA

06 i 7 10 J 10]'O

Time after final shutdown (sec)

Fig..2-4 Specific activities of inboard TF coll casingall

- 19 - ~ ~ ~ ~ - A--Co5

JAERI-Tech 2002-083

3. Clearance Potential of Components

3.1 Clearance Level

For extremely low-level radwastes it may ignore the human risk because of their

small impacts with regard to radiation. Recently, concept of 'Clearance' has been

discussed in many countries and the unconditional clearance level has also been

specified in some countries. The clearance from regulatory control implies a removal

of restrictions so that the cleared components can be treated without any other

consideration of their radiological properties. Because of no specified site in the

current design of ITER, the unconditional clearance level given in IAEA documents

is tentatively applied to this study. The approach applied to the IAEA document is

based on the probability of occurrence and constrains dose rate for 'Likely event' to

10 iSv/year and that for 'Unlikely event' to 100 jiSv/year.

The technical document of IAEA-TECDOC-855 "Clearance Level for

Radionuclides in Solid Materials" 31 was used for evaluating the radwaste level in

this analysis. This document includes the investigation results with regard to the

clearance levels of solid radwaste, and it is not an international standard.

The concrete values for the IAEA clearance level are calculated on the basis of

published technical papers that provide the results of evaluation routes for solid

waste disposal. Ranges of the clearance level (e.g. 0.1Bq/g - Bq/g) are specified

for each radioisotope in the AEA-TECDOC-855. The representative single values

and low values of activity concentration described in IAEA-TECDOC-855 are shown

in Table3.1-1. In this report 'Low value' of IAEA-TECDOC-855 is adopted in the

assessments of clearance potential while 'representative value' was used in ITER-

GSSR.

Figure 3.1-1 shows the comparison between two criteria of the clearance level

for major isotopes that will contribute to the clearance potential. The representative

values normalized by the low values are shown in the figure. For `0Co and 94Nb, the

representative value is 5 and 4 times larger than that of the low value. Also for 99Tc

the representative value is 7.5 times as large as that of the low value. On the other

hand, the representative values are smaller than the low values for ` 5Fe and 13Ni.

When a material contains several radionuclides, the following formula is applied

to evaluate the clearance possibility;

ECil/Cii 1i=1

where Ci is the specific activity of the radionuclide i in the material and Cli is the

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JAERI-Tech 2002-083

clearance level for that radionuclide.

3.2 Clearance Indices

According to the clearance level given in AEA-TECDOC-855-Low, specific

activities in major components were categorized into radioactive waste (radwaste)

and cleared waste. For tokamak components the following 17 isotopes are relevant

with regard to clearance.

'H(half life: 2.3y), 14C(5.7x10 3y), 3 2p( 14.3d), 35S(87.5d), ` 1Cr(27.7d),54Mn(312.1d), 55Fe(2.7y), 59Fe(44.6d), 57Co(271d), ' 8Co(70.8d),60Co(5.3y), 9Ni(7.5x 10 4y), 63 NM(100.1ly), 90Y(64.1lh), 14Nb(2.Oxl10 4y),99mTc(6.0h), 99Tc(2. 1X10 5y)

Clearance potential for High-Ni and High-Mn cases at appropriate period after final

shutdown, e.g. 30 - 40 years, are investigated for TF coil casing, VV shells, VV shield

materials and blanket shield block.

3.2.1 High-Ni Case (current design)

Clearance indices based on IAEA-TECDOC-855 for High-Ni case are shown in

Figs.3.2-1 to 3.2-3. Both clearance indices based on "representative value" and "low

value" are added in these figures. For TF coil casing (see Fig.3.2-1) clearance index

at the surface of inboard coil casing shows the clearance level at about 75 years after

final shutdown for the "representative value" case, and about 90 years for the "low

value" case. The outboard TF coil casing can also reach to the clearance level at

about 30 years and 45 years after final shutdown for the "representative value" case

and the "low value" case, respectively.

The outer shell of outboard vacuum vessel has clearance potential at about 30

years after final shutdown for the "representative value" case, and about 40 years for

the "low value" case (see Fig.3.2-2). The outer shell of inboard vacuum vessel will

reach to the clearance level at about 90 years for "representative value" case and

about 100 years for "low value" case. Difference of the clearance potential between

inboard outer shell and outboard outer shell originates in the vacuum vessel

thickness (inboard: 337mm, outboard: 750mm).

For blanket shielding block the clearance index does not show the clearance level

even if the decay time after final shutdown exceeds a few hundred years (see Fig.3.2-

3). Figure 3.2-4 shows the clearance index for the shield material of outboard

vacuum vessel at 30 years after final shutdown. Clearance indices of plasma side

surface (inner surface) and outer surface of the shield material are around 50,000 and

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JAERI-Tech 2002-083

2, respectively. In High-Ni case shield materials of the vacuum vessel do not reach

to the clearance level at 30 years after final shutdown.

3.2.2 High-Mn Case

Clearance indices in High-M~n case are shown in Figs.3.2-5 to 3.2-8. In this case

IAEA-TECDOC-855-Low values are applied to the assessments of clearance potential.

Clearance indices of the TF coil casing are shown in Fig.3.2-5. The indices are given

for 3 positions of two inboard and one outboard coil casing points. For inboard coil

casing (see Fig.2.1-2), the nose region reaches to the clearance level at around 30

years after final shutdown, but the surface of plasma side can not reach to the

clearance level within 100 years after shutdown. For the plasma side surface of the

outboard coil case, about 25 years are necessary to reach to the clearance level.

Figure 3.2-6 shows the clearance indices of the vacuum vessel shells. Specific

activities at the surface of the shells are assessed for the clearance potential. For inner

shell of the vacuum vessel the clearance indices cannot show the clearance level up

to 100 years after final shutdown. The inboard outer shell also remains above the

clearance level beyond 100 years. However, the outer shell of the outboard vacuum

vessel has clearance potential at about 30 years after final shutdown.

Figure 3.2-7 shows the clearance indices of the blanket shield block. These

components remain above clearance level beyond 100 years. Figure 3.2-8 shows

also the clearance index of the vacuum vessel shield material at 30 years after final

shutdown for High-Mn case as well as the High-Ni case. For High-Mn case, small

area near the rear shield material will reach to the clearance level. The clearance

index for High-Mn case is one order of magnitude below the High-Ni case.

.At the ITER decommissioning point of view, there are 8 isotopes that are relevant

with regard to clearance up to 100 years after final shutdown. These isotopes are3 H1, 14C, 54Mn , 55Fe, 60CO, 63Ni, 'Nb and 99Tc. Up to 60 years after final shutdown, the

clearance indices are dominated b y 6 Co. Beyond about 60 years, 14 Nb becomes a

dominant isotope. Detailed analysis results are presented in Appendix-2.

Comparison of the clearance potentials between High-Ni and High-M~n cases is

summarized in Table3.2-1. High-Mn case has a potential benefit for the clearance

possibility of the outboard TF coil casing. Around 3,000 tonnes of the radwastes are

reduced in the High-Mn case at 30- 40 years after final shutdown. Details are

discussed in section 5.

-22 -

JAERI-Tech 2002-083

Ln >Ln a,

> C� c en e M n en cn Cn cn cn en e M cn en< 0 0 0 c c 0 0 0 c c c'4�' m cn 6 en M d rn - . . . . . . . . cj en

Ln

ui

al 0 (0 N N (m N 1* CO CO CO0 0 o - m N m . . . 0 0 G J 0 -can 0 CS Ln 0 0 0 0 0 0 c; 0

Ln a) m Ln m- Ln CO cnca m (n cnm2 7 7 7 -0 n 0 -r A- -r-

Q 0 cn0 en C 0 cn 0 C) Cl cn 0 (D (n 0 (V)CY CS 6 0 Q o 0 c) 6 en cnc CD 0 cf)M cn Cf) (f)

_i0 0 c 0 C Ln C) 0a 0 0 0 (M o C Ln CV) 0C> 0 o (0 Tr

C' o ri C) .. 0 't 0 0 0 CSN 00

N 1* L, W Ln L, 0) r- ooo Ln 0) CD a)nt N cnen N N (n cn m Ln Ln Ln Ln LnW0 (b ch CL m 1� 1 4 6 6 68 z z U 2 LL u~ U U z N U)

23

JAERI-Tech 2002-083

CU ~~c jcc;cUc

2 2~~~~~~~~azz22 CJ~~~~~~~~~~ C~~CJc c

FE2

CB C

U.) ~~~cj C Z- Z_ Z Z c A

ez c C C.) U cu c eU

CU ~~~~~~~~~~~~~~~~~~~~~~CU C~~~0

-~~~~~~~~~ 00 00 c11T UC 0Z 2z2 z z z z z z

U.) z z z -C

-~~~~~~~~ CU~~~~~~~~~~~~c C

0.) CU CU n~~~~~ CU CUC

m ) E 2 CU CU 0 Um ) U - 50CU 0'L

0 U tt .-- 4c c 0 . 0 W 3 -r U CU

U cj U ) U

U() ~ w U-~ UCUCCUC24

JAERI-Tech 2002-083

100 1 T

0

>

0w

H-3 C-14 Mn-54 Fe-55 Co.60 Ni63 Nb-94 Tc-99

Major Radionuclides

Fig.3.1 -1 Comparison of clearance level between TECDOC-855-Average

and TECC-855-Low

- 25

JAERI-Tech 2002-083

- - - - - - -~- E-igh-N ra-inboard

11+03 ~~~~~~~~~~~~-Hig-Nirot-outr a

1E+01 __

.E-02_ _ _ _ __ _

E-0…

0 10 20 30 40 -50 60 70 80 90 100

Time after Final Shutdown (year)

Fig.2-1 Clearance indices for covsl cshel (current design; High-Ni case)

1.11+07~- 26

JAERI-Tech 2002-083

1.E+09

1E+08

1.E+07HiNrerutod

1.E+06

1.E+05.

L.E+04

L.E+02,__

11.+s01 Blanket shield blocks are categorized into radwastesfor both dlearance index (TECDOC-855-Average and TECDO(>855-Low)

1.E+0O a io 20 30 40 50 60 70 80 90 100

Time after Shutdown (year)

Fig.3.2-3 Clearance indices for blanket shield block

(current design; High-Ni case)

inner shell shield material outer shell

1.E±06,

L E+04.

1.E+03~

E+2innersurfaceofshield material ___11+01 -~ ~ ~ ~ ~ ~ 1 -

11E+couter su rface of shield materia

1.E-al I-10 0 10 20 30 40 50 60 70

Distance fromn the VV inner Sheli (cm)

Fig.3.2-4 Clearance index of outboard VV shield material

at 30 years after final shutdown (current design; High-Ni case)

- 27 -

JAERI-Tech 2002-083

10 A

I -~~~~~ l~~nbcnr1 T Ci Casing Nose regionio4 .. -a--.... ...... .. Inboard F: Coi Casing -Piasma side4 0 ~~~~~Outboard TF Coil Casing Plasma sid

i 3

00 2

o '

1 01 k ~ .C

10 102 040tt6 0 09 0

1 Ut¶7

10 % *,

i 3

10 1 J ± J i JL....J......L.....L................................ ...........

C 10T1 ~~~~6 Inboard VV outer shell~~~~~~~~~~~~~~~~~~~~

tttfttq-4-

Timeafte Finl Sh-A-w -(Inbar)Vine hl

Fig.12-6 Cearance idices forv-cu @m-vuteloardVl irghl cse

- 28- U I --

JAERI-Tech 2002-083

8 Outboard blanket Sh eld Plasma aside1 0 ..... ..... ......

Outboard Blnt Shield side

7 ~ -I

00od 1 0

w ) . . . . .. . . . .. . . . .. . . . .. . . .. . .. . . . .. . . .. .. . . . .. . . . .. .

100.

0 03 4 06 0)09 0

_ 10~~~~Tm ftrFia hudw.(er

Fi1) - laac nie o lne hedbok(ihM ae

ine hl hedmtra ue hlC~~~~ -~~ ic~FiI.E

LE1) .

LE0

100 10 20 30 40 50 60 7080 9 10

imne afterFhnal ShudneShl (ea)

Fig.2-8 Clearance indcs o blne shield blocka a (HghM ease

i anrtselia hudw HihN n shieldM outerhl

~~4 ~ ~ ~ 29

JAERI-Tech 2002-083

4. Activation Level of Radwaste

Actual quantity or concentration limits on classification of the radwastes will be

established by the regulatory body of the host country. In this section the

categories of the major tokamak components (TF` coil casing, vacuum vessel, blanket)

are investigated on the basis of the classification of the radwastes for its safe disposal

in Japan.

4.1 Classification of Radwaste

In Japan, radioactive solid wastes are classified into two levels for regulatory

purpose. At present, categories of 'High-level' and 'Low-level' are defined for the

radioactive wastes. The high-level radwaste is defined as the highly radioactive

material resulting from the reprocessing of spent fuel, including liquid waste

produced during reprocessing and solid materials derived from such liquid waste.

Subsequently, the low-level radwaste in Japan is categorized into 3 classes (Li: high-

beta and gamma waste, L2: low-level waste, L3 : extremely low-level waste) given in

Appendix-3. In accordance with the radwaste classes, appropriate approach for

final disposal is taken into account.

Representative values of the activity concentration for the radwaste category are

summarized in the following table;

[Classification of solid radwaste (Bq/ton)I [41L1 waste (high-beta, gamma) L2 waste (low-level) L3 waste (extremely low-level)

H-3: C > 150P** H-3: 3.OG* <• C < 5OP** H-3: C < 3.OG *

C-14: C >37G* C-14: II1OM*•<C< 37G* C-14: C < 1M*K-40: CŽ> 170M** Ca-41: 5OM* <•C < 3.1 G* Ca-4 1: C < 150M*Ca-41: C Ž 3.1G* Co-60: 8.1G* < C < II .LT Co-60: C < 8.1G*

Co-60: C> Ž I. IT* Ni-63: 7.2G* < C < . IT* Ni-63: C < 7.2G*Ni-63: C > 1. 1 IT* Sr-90: 4.7M * < C < 74G * Sr-90: C < 4.7M*Sr-90: C > 74G* Nb-94: 8M** < C < I IG** Nb-94: C < ISM* *

Nb-94: C 1 G** Tc-99: 9.OM** < C < 190M** Tc-99: C < 9.OM**Tc-99: C>190M** Cs-137: l00OM* 5C <1.llIT* Cs-137: C <l00M*Cs-137: C Ž: .IIT* Eu- 152: C < 360M* Eu-152: C < 360M*Eu-I152: C Ž 360M* an alpha emitter: C < 1. 11 G* an alpha emitter: C < I17M*

an alpha emitter: < 1.ll G*[Notes]

A value with a single star-mark ()is quoted from the Article 13-9 of the government cabinet No. 324 for "thelaw for regulation of nuclear source material, nuclear fuel material and reactors".

A value with a double star-mark (**) is not enacted yet, but it is used in the examination of safety approaches forradwaste disposal that the government has held.

4.2 Categorization of Radwaste

Activation levels of TF coil casing, vacuum vessel shell and blanket shield were

investigated on the basis of the above radwaste classification. Results of the

activation calculation for High-Ni and High-Mn cases are assessed in this section.

- 30 -

JAERI-Tech 2002-083

4.2.1 High-Ni Case (current design)

In ITER it is noted that there is no "High-Level" radwastes due mainly to low

neutron fluence (-0.3 MWa/m2 ), so that the assessment is concentrated to provide

the major tokamak components to be categorized into which classes. In accordance

with the classification of radwaste level, L2 and L3 limit indices for TF coil casing,

vacuum vessel and blanket shield block are shown in Fig.4.2-1 and Fig.4.2-2,

respectively. TF coil casing is categorized into L3 at 30-40 years after final

shutdown. For vacuum vessel shells, the outer walls of inboard and outboard

regions fall into L3 after 30-40 years. The inner walls of the vacuum vessel shells

will reach to the L2 limit at 30-40 years after final shutdown, but marginal. If the

neutron streaming between the adjacent blanket module gaps were relatively high,

the inner walls will be categorized into Li. For blanket shield the front (plasma

side) surface is categorized into Li and the rear one is categorized into L2.

Limit indices of major isotopes are shown in Figs.4.2-3 to 4.2-8. Technetium-99

dominates the L2 limit indices for each component at 30 - 40 years after final

shutdown. On the other hand, the L3 limit indices are dominated by 60Co up to

about 20 years, and by `3Ni and ' 9Tc beyond about 20 years after final shutdown,

respectively. According to these analysis results, reducing Ni, Co and Mo contents

in the steel appears to be effective for reducing the activation level. The L3 limit

index of vacuum vessel shield material (outboard region) at 30 years after final

shutdown is shown in Fig.4.2-9. Taking account into the summation of the L3 limit

indices of each isotope, material within 20mm in depth from outboard inner shell is

categorized into L2. Subsequently, approximately 2/3 of the outboard shield

material will be categorized into L3. For inboard shield material all region will be

categorized into L2 since the thickness of the inboard shield material is as small as

217mm (cf. 630mm for outboard).

4.2.2 High-Mn Case

L2 and L3 Limit indices for High-Mn case are shown in Fig.4.2-10 and Fig.4.2-11.

For TF coil casing, both of inboard and outboard casings are categorized into L3 with

a sufficient margin at final shutdown. The inner shells of the vacuum vessel are

categorized into L2. A magnitude of margin for L2 limit is maintained in the High-

Mn case. Induced activities in the outer shells of the vacuum vessel are well below

the L3 limit at final shutdown. The near surface of the blanket shield block cannot

reach to the L2 limit during 100 years after final shutdown. The activity at rear

surface of a blanket meets the L2 limit at final shutdown. It is noted that the

- 31 -

JAERI-Tech 2002-083

activities of the separable first wall materials such as beryllium, copper-alloy and

small amount of stainless steel are not assessed in this study because of regularly

exchange parts. Main isotopes that contribute to L2 and L3 limit index are as

follows;

[For L2 limit index] [For L3 limit index]

TF coil casing ` 3Ni, 4̀C TF coil casing : 6̀ Ni, `4C

VV shell : 63Ni, 99Tc VV shell : 63Ni, 14c

Blanket shield: 14C, 63Ni Blanket shield : H, 14C

Details are presented in Appendix-4.

For the shield material of the outboard vacuum vessel, L3 limit index at 30 years

after final shutdown is shown in Fig.4.2-12. Taking into account for the summation

of the L3 limit indices of each isotope, about 10mm depth from outboard inner shell

is categorized into L2. Approximately 1/6 of the outboard shield material is

categorized into L3. It also shows that 1/2 of inboard shield material is categorized

into L3.

Table4.2-1 shows the summary of the categorization of the components for High-

Ni and High-Mn cases at 40 years after final shutdown. It is clear that the High-Mn

case has advantages for reducing activation levels with regard to rear region of

blanket shield, VV inner shell, VV shield material and outboard TF coil casing,

resulting in easier decommissioning process.

- 32-

JAERI-Tech 2002-083

Table4.2-1 ITER radwaste classes for high-Ni and high-Mn steels at 40

years cooling

Component Region Radwaste Classes

High-Ni Steel High-Mn-Steel

Blanket Inboard front/rear Li/Li L1IL2

outboard front/rear MLL Ll/L2

Vacuum Inboard inner shell Li L2Vessel

Inboard shield block L2 L2/L3 *11

Inboard outer shell 1,3 L3

Outboard inner shell Li L2

Outboard shield L2/L3 *21 L2/L3 [*3]block

Outboard outer shell L3 L3

TF coil case inboard L3 L3

outboard L3 < Clearance level

[Notes]

*Clearance: Low value of IAEA-TECDOC-855

*11 In the High-Mn case -1/2 of inboard shield block will be classified into L,3 radwaste.

*1 In the High-Ni case -1/3 of outboard shield block will be classified into L,2 radwaste.

*[*3] In the High-Mn case -'-1 /6 of outboard shield block will be classified into L2 radwaste.

-33 -

JAERI-Tech 2002-083

L.E+0.

- Moil case-inboardI.E 00 ________ -~~~~~~~ -~~- VVI-rear-inboard

I ________ ~~~~~-*eW- lanket-front-outboard

-0-- lnanket-rear-outboard.C lEM U Vfront-outboard

-B- VV-rear-outboard~2 .E-02. -- TFeoil ~aeoutboard

L.E-04._ _ _ _

I.E-052 -

1.E5-O(0 20 40 60 W5 100

Time after Final Shutdown (year)

Fig.4.2-1 L2 limit index for major tokamnak components

(High-Ni case)

L.E+05.

-~~ _______ - .... ~~TFeoil caswe-inboard1.E±03 - 6- - VV~~~~~~~~~~~-rear-inboard

x 11+02 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~~~- Blanket-front-outboard1.E+02 --- ~~~~~~~~~~~~~~~ Blanket-rear-outboard

-- VVfront-outboard*~1.+01 -a- V-riear-outboard.

T~co case-outboardI .E+00i~.

1.E-02 ._ _ _ _

1.E-03 _ _ _ _ _ _ _ _

l.E-04.o 20 40 60 80 100

Time after the last Shutdown (year)

Fig.4.2-2 13 limit index for major tokamnak components

(High-Ni case)

- 34 -

JAERI-Tech 2002-083

I .- 02

L.E-03 1

*-.-.~~ C-14-inboard

*.U--~~~.. ..... ..... _. CO -60-inboard

1.E-05 -a.NI -6-inboard

TC -99-inboard

1.11E-06 --- C - 14-outboardC4

-U--CO - 60-outboard1.1E-07

~-NI - 63-outboard

L E-0S___ ___ ___ - TC - 99-outboard

L E-09

1.1E-100 20 40 60 s0 100

Time after the final Shutdown (year)

Fig.4.2-3 L2 limit indices for typical isotopes in TF coil casing

(High-Ni case)

.100

1.E-02 ____... CO-60-inboard

-. ~.NI -63-inboard

CO -60-outboardI .E414 - - .-.u-- ~~~~~~~~~~NI - 63-outboard

--- TC -99-outboard11.-05

11E-06.

1.E-07

Time after the last Shutdown (year)

Fig.4.2-4 [3 limit indices for typical isotopes in TF coil casing

(High-Ni case)

- 35 -

JAERI-Tech 2002-083

______ - -- - rar-inboard-C-14

L.E-01 _____ -- rear-inboiard-Co -60

* A-rear-inboard-Ni -63

*..rear-inboard-Ic -99

~~ 1.E-03 -. ~~~~. ............ _. .... . front-outboard-C-14

f.~ ront-outboard-Co - 60

L 1E-04 h- .. .

front-outboard-Ni -63

1.E-05 - front-outboard- Tc -99

'cl r#~~~~~. ar-outboard-C- 1 4

--- rear-outboard-Co - 60

07 ~ ~ ~ ~ ~ ~ ____ a-rear-ob-Ni - 63

--- rear-o-ilc -991 E -0 8.................. ........... .... ..

0 20 40 60 so 100

Time after Final Shutdown (year)

Fig.4.2-5 L2 limit indices for typical isotopes in VV shells

(High-Ni case)

- -rear-inboard-Co -60

LE+00;h.. ~ ~ ~ ~ ~ ~ ~ ~~~~~~~--a--rear-inboard-Ni -63

i.E-Oi - ~~~~~~~~~~~~~~~~- rear-inboard-Tc -99

A **.-*....... rear-outboard-Co -60

41, a. rear-outboard-Ni -63

--- A&- rear-outboard-Tc-99

LE-041M a ~ ~ ~ ~ ~ ~ ~ ~~~~~~- fronit-outbo,,ard-Co -60

________ ________ -~~~~~~~i arnt-outboard-Ni -63

.- front-outboard- Tc -99

0 20 40 60 s0 100

Time after the last Shutdown (year)

Fig.4.2-6 L3 limit indices for typical isotopes in VV shells

(High-Ni case)

- 36 -

JAERI-Tech 2002-083

1.E-i-02. -- ~~~~~~~~~~~~front-outboard-C-14

-- front-outboard-Co -60

L E+( front-outboard-Ni -63

-w- front-outboard- Tc -99

-~rear-outboard-C-14

-*- rear-outboard-Co -60

_________ _________ 4- rear-outboard-Ni -63

rear-outboard-Tc -99

0 20 40 60 80 100

Time after the final Shutdown (year)

Fig.4.2-7 L2 limit indices for typical isotopes in blanket shield block

(High-Ni case)

- - - 4--4'---~~~~~~~~~~ rear-outboard-Co -60

I.E 1. - -.--- rear-outboard-Ni -63

1.E4-0] -a- ~~~~~~~~~~~~~~~rear-outboard-Tc -99

LE*00 fotoutboard-Co -60

11 -Ol -c-~ - front-outboard-Ni -63

1 .1-02 _ ___ -A- front-outboard- Tc -99

1,E-03.

11.-04.

L E-05 ____

o 20 40 60 80 100

Time after the last Shutdown (year)

Fig.4.2-8 1,3 limit indices for typical isotopes in blanket shield block

(High-Ni case)

- 37 -

JAERI-Tech 2002-083

CO

C")~~~~~~~c

C:)~~~~C

U~~~~~~~~~~~~~~~~

C) C) C? C?~~~~~0 C

38 -~ ~ ~ ~ -

JAERI-Tech 2002-083

- * l nboard-TF coil case -front-ClD - - nboard-VV outer shell -front

-- l nboard-VV inner shell -front10 I ~Outoard BLsheld fro t

Outboard-BL shield earWOuboard- i'~nner shel -f ont

10 ......................- - Outoc~rd Vo ter shel froa-0 Outboard-TF coil case front

0

1 01

10-

(N 0 ......

1 06

1 0

0 1 0 20 30 40 50 60 70 80 90 100

Time after Final Shutdown (year)

Fig.4.2-10 12 limit indices for TF coil casing, VV shell and blanket shield block

::*:lnbo ard-TF coil case -front--0 - nboard-VV outer shell -front

E- -lnboard-VV inner shell -front'I5 _______O____]~ utboard-BL shield -front

10.~~~~~~- Outboard-BL shield -rear-~0utboadVV inner shell front

1 ~~~~~~~~~-)Outbcaid-VV outer shel front

10O

E 10 -

-j 1

.m.. .. .…

-3

-4

1 0-

0 20 40 60 80 100

Time after Final Shutdown (year)

Fig.4.2-11 L3 limit indices for TF coil casing, VV shell and blanket shield block

- 39 -

JAERI-Tech 2002-083

U)~~~~~~~~~~~~~U

C) () Q) C

Co II! iiC-

- -- - 0) - 40

JAERI-Tech 2002-083

5. Preliminary Estimation of the amount of Radioactive Wastes

In accordance with the above assessments, the radwaste masses for blanket

modules, vacuum vessel and TF coils are roughly estimated. Comparison result of

the radwaste masses between High-Ni and High-Mn cases is shown in Fig. 5-1. At

the end of ITER operation, total radwaste volume/weight is almost same in both

cases. However, quality of the radwastes is deferent, i. e., Li in case of High-N is

larger than that of High-Mn, while L2 in the former case is smaller than that of the

latter case, giving some cost saving at the decommissioning period.

Up to 30 years after final shutdown, total mass of the ITER radwaste is still same

in both cases, but small improvement for Li waste is expected in High-Mn case.

(about 300/ lower than that in High-Ni case) Also amount of Li and L2 wastes in

High-Mn case decrease to around 2,800 tonines while 3,300 tonnes in High-Ni case.

At 40 years after final shutdown, some of L3 wastes ( 3,000 tonnes) will reach to

the clearance level in High-Mn case so that the total mass will decrease to 11,500

tonnes. On the other hand, they are still over 14,500 tonnes in High-Ni case, which is

the same as that at 30 years after final shutdown.

-41 -

JAERI-Tech 2002-083

0113 (extremely low-level)

1 .6E+04 a__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ *L2 (low-level)ELi (high-beta, gamma)

1 .4E+04

1. 2E+040

1.0E+04

8.O1E+03

6.OE±03

4.0E+03

2.0E+03

0.OE+00at final shutdown 30 years 40 years

Time after final shutdown (year)

a) Current Design (High-Ni steel case)

1 .6E+04 __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 013 (extremely low-level)a*L2 (low-level)ELI (high-beta gamma)

1.4E+04

1.21E+04

lj 1.OE+04 .~.

8.OE+03

4- 6.OE+03 --- ~ -

0

4.OE+03

0.0E+00at final shutdown 30 years 40 years

Time after final shutdown (year)

b) High-Mn steel case

Fig.5-1 Remaining radwaste masses after final shutdown for blanket,

vacuum vessel and TF coil

- 42 -

JAERI-Tech 2002-083

6. Conclusions

Employing less Ni and Co steel in place of high Ni austenitic steel for blanket

shield block, vacuum vessel shield material and TF coil casing has been studied as

one of the effective ways to reduce the activated materials at the decommissioning

phase. Idea for material changes is to play roles of reducing the radioactive wastes

and its radiation level for TF coil casing and of reducing activation levels for the

shield blocks. Based on the systematic analysis, assessment of the activation level

and brief radwaste mass estimates are performed. It believes that reduction of

amount of the radioactive wastes gives effective cost saving at the decommissioning

period. Major results are as follows;

1) The outboard TF coil casing for High-Mn case has the clearance potential at 30

to 40 years after final shutdown while it will be practically difficult for High-Ni

case.

2) Compared to High-Ni case, additional 3,000 tonnes of the radioactive wastes

will be moved to clearance for High-Mn case at 30 to 40 years after final

shutdown.

3) The inner shells of the vacuum vessel are categorized into L2 (low-level) for

High-Mn case in accordance with current Japanese regulation, but on the other

hand the shells for High-Ni case remain in the Li (high-beta, gamma) at 30 to

40 years after final shutdown.

To apply this concept to the ITER project, it is necessary to provide further

evaluations such as the material applicability, fabricability, compatibility with the

related components and acquisition. In particular the fabricability for magnet

structure, the weldability is the most important issue so that R&D study is

intensively ongoing as a part of demonstration of fabricability for ITER CS jacket

material. For change of shield material, it will be less problem because of no

structural components and simple structure.

-43 -

JAERI-Tech 2002-083

Acknowledgements

The authors would like to express their gratitude to Dr. . Shoji, member of

Department of ITER Project and Drs. H. ida, J. Reader of ITER International Team

for their valuable discussions and comments. They also would acknowledge Drs. T.

Tsunematsu, T. Takatsu, M. Seki, S. Matsuda and Dr. H. Kishimoto for their support

and encouragement.

References[1] Generic Site Safety Report (GSSR), Volume V, "Radioactive Materials,

Decommissioning and Waste", G84 RI 4 01-07-06 R 1.0, 2001.

[2] Y.Seki, H.Iida, H.Kawasaki and K.Yamada, THIDA-2: An Advanced Code Systemfor Calculation of Transmutation, Activation, Decay Heat and Dose Rate, JAERI1301, March 1986.

[3] "Clearance Level for Radionuclides in Solid Materials", International AtomicEnergy Agency, IAEA-TECDOC-855, Vienna, 1996.

[4] Classification of radwaste for its safe disposal in Japan, November 24, 2001.

-44 -

JAERI-Tech 2002-083

Appendix-i

Specific activities of TF coil casing, vacuum vessel and blanket

- 45 -

This is a blank page.

JAERI-Tcch 2002-083

Analysis cross section

Vacuum Vessel ~~~~~Vacuum Vessel

Shi el ding Bl anket Shielding Blanket 41 1617

Inboard Region Materas . .Outboard RegionSurface of CS coil c ace CS Coil 12 Bl anke s hiel d - 1

2 TF coil case - 1 Structual material: 55316WN3 - ~~~~~~~~~~~~~~Conductor Nb3Sn 13 Blanket shiecld - 2

iT coil case 2 *T~~~~~~-F Coil 14 VVinner wall - 14 IF col case - 3 Structual materi al: JK2 1 5 VVinner wall - 25 TF coilI case - 4 _conductor Nb3Sn 16 Voue al

6 VV outer wall - 1 ~~~~~~.Vacuum Vessel 16____ wi 6 W outer W all - 1 -Structual material: SS316LN 17 VVouter w al I- 2

7 VV outer w all -2 _Shield material : SS204L- 18 TF coil case - 1

8 VV inner wall 1- -Shielding Blanket 19 IF coil case - 29 VV inner wall -2 FW e/Cu/SS316LN

10 Blanet shicl cl 1 _~Shie Ldmaterial : JK2 20 IF coil case - 310 Blanket shield - 1 ~~~~~Tlrmal Shield 21 IF coil cas - 4

11131Blanket s hiecldc - 2 Structual material : SS3161LNSurface coating: Ag

Analysis points

-47

JAERIVTech 2002-083

-ALLinduced activity (r-21 5.66cm) -.-- FE -55

1 .OOE+01 -- CO -60

NI-63

1.OOE+00 - -- -- ----- -4- MN -54

1.OOE-01 ~ ~ ~ ~ ~ ~ ~ ~ 4*CO -57

MO-93

1.0OE-02 .......... NI ~~~- 59

& B- 93m1.OOE-03 ... --.

-U4&-V -49

1.GOE-04 -- ....- 4' - £ - -4- C -14

1.OOE-05

1.001E06 ... .. .. m ...TC -99

1.OOE-07 91K~----

1.OE+07 1.OE+08 1.OE+09 1.OE+10 ---O --- FE -59

Time after final shutdown(sec) - A--- -35

CS coil casing (analysis point - )

induced activity (r=221 .3cm) - L1.OOE+04 *~~~~~~~~~~~.---FE 65

-A-CO -60

-- NI -63

1.OOE+0 --------- - ------ -4- MN -54

1.00E4-01- --------- e - 57IN-MO 93

-O-NI 59

~~, 1.OOE-O1 - -A--~~~~~~~~~~~~&Ne - 93m

b.CE-0 1-- U-V -49

-- C -14

o --4--~~~~~~~~~~~~~~~~~~H - 31 .OOE-04 ------ A-A

--A-NB -94

lOCE-OS ------ -- -----

1 .OOE-06, ---X-'.-X ---- --x - ---- x rx -4-CO -58

--- X- NB -91

--- X- MN -53

G-FE -591.1DE+07 1.OE±08 1.OE+09 1.OE 1 0

---h--S -35Time after final shutdown(sec) -

Inboard TF coil casing-I1 (analysis point -2)

48 -

JAERI-Tech 2002-083

-ALL2induced activity (r=240.99cm) -.- FE -55

1.13OE+06 ~ ~ ~ ~ ~ ~ ~ -ACO -c0

1.0011+04' 5 ~~~~~~~4-MN -54

1.001E+03 ........ )q CO ~~~~~~~- 57

1.OOE+02 M MO~~~~~~~~~~~~~~~-93

g1.OOIE±O1 *--- -0-NI -59

31 1.OOE-i-O - -- NB -93m

1.0OE-01 R V ~~~~~~~~~~~~~~~~~~~~~- 49

1.OOE-02 0 ~~~~~~~~4-C -14

U 1OO0E-03 --- H - 3

----IE04 ----- - -A -- B -9

1.IOOE-05 ---- -.- - -T -9

1.00IE-06 ~ ~ ~ ~ ~ ~ ~ ~ -4-CO -

100OE-07 ---X-NB 9

1 .OOE-08 ~~~~~~~~~~~~~~~--- X- MIN-53

1.OE+07 LIDE+08 1O0E+09 LOE+10 FE -59

Time after final shutdown(sec) --- -- - 3-5

Inboard TF coil casing-2 (analysis point -3)

induced activity (r-300.54cm) -ALL

__ __ _ __ __ _ __ __ _ __ __ _ __ __ _ __ __ 4- - F E -55

-ACO -860

-- NI 863

-4-MN -54

-% CO 57

Z1.OODE+04 ---

1.OOE+02 ib ~~~~~~~~-ANB -93m

-B--V -49U1.OO1E+01

-- C 14o1.OOE+OO

1.OODE-03 - CO -

1.OOE-04 1 ---------- X- NB -91

1 .OOE-OS ---IN-~~~~~~~~~~~~~~~- MN -53

1O0E+07 1.OE+08 LO0E+09 1OE+1O --- 0- FE-SB9

Time after final shutdown(sec) -35_

Inboard TF coil casing-3 (analysis point -4)

- 49 -

JAERI-Tech 2002-083

induced activity (r=306.96cm)-- FE-5

LOOE+08 CO ~~~~~~~~~~~~~~~~- 60

- -- -- ----- ~~~-U-i- NI -63

LOOE+06 ~ ~ ~~~~~~~~--MN -54

CO-57

--MO -933 1OOE+04 ~.--N 5

L OOE+03 --- ---NB -93m

1.00E+02 *" -- --- --- V -49

. - 14

~~ 1.OOE+0O ~ ~ ~~~A __ ---- - H - 3

)1 .OOE-00 -- ~~- os

--- -- NB- 94

LOIDE-03indued- ctiit------cm -- ---X NB-9

LOOE-04 -------- VI~~~~----- N 54

LOE02 FE -

- --------- -------- m--

1.OOE-02 - - iduedac -ty r32-Om-- AL---

LOIDE+05 --------- ............ X--NB-9

L.0DE-04 --- .... .. ------------ --- CO - - -57

m NI ~~~~~~~~~~~~~~~-- --- 59

1.1 +7 10+6 10+9 LE+02-A-S3Time after final shutdown~~~~~~~scNB- 93m

1.O1I"oar VVouerwllIVaalsi oit96

- 50 -~~~~~~~~~~~0 C 1

JAERI Tech 2002-083

-ALLinduced activity (r=329.Ocm)

--4--FE- 55

1.OOE+07 ~ ~ ~ ~ ~ ~ ~ ~ ~ -*-CO 60

1.OOE+06 ~ ~ ~ ~ ~ ~ ~ ~ ~ -- NI 63

-4-MN -54

CO-57

1.00E+04 M MO ~~~~~~~~~~~~~~- 93

1. *-40-NI 59

1.OOE+02 ~ ~ ~ ~ ~ ~ ~ ~ ~ -A-NB 93m

-U9--V -49

1.OOE+01U -4-C -14

--- HC-3

1.0011-01 ~~~~~~~~~~~~--AX- NB- 94

1O0OE-02 ---i---N-5

---- NB- 91

L.OE+07 1.OE+08 1.OE+09 1.0E-.10 --- &--S -35

Time after final shutdown(sec) --- ZR -93

Inboard VV outer wall-2 (analysis point -7)

Induced activity (r=35 1.8cm) -ALL

0 E- 55

-60

-4-MN -54

-- CO -57

Z1.OOE+06 .... MO-9

N-59

ONB- 93m

> 0 ~~~~~~~~~~~~~~i-V -49

-14

cj .~~~~~~~~~~~~~~~~-4 -- H -3

--A- - NB -94

1OO0E+0 2m.. g-m - --- - *-

1.OOE+OO.-.-i-- MN -53

1.OOE-O1 0-- FE -59

LIDE±07 LOE+08 1OE1+09 1.OE+10 -- 3

Time after final shutdlown(sec) ---4a ZR -93

Inboard VV inner wall- (analysis point -8)

51

JAERI-Tech 2002-083

-ALLinduced activity (r=356.8cm)

E- 55

1.00IE+09 ~ ~ ~ ~ ~ ~ -ACO - 0

- -63

--MN -54

1.01DE+07 ~ ~ ~ ~ ~ ~ ~ -NCO- 57

-1.OO1E+0 -- MO -93

-Q-NI -59

1.001E+05 ~~~~~~~~~~~~-f-NB -93m

-- V -49

z 1.OOE+04 ~~~~~~~~~~~~~ -0C 14

-4 DE0 7 4

1OODE+0;X

1.OOE-i-01 - - ~~-M--------- 4;-

---- NB- 91

---E--MN -53

1 .OOE-O1 ~~~~~~~~~~~~~~~~~-- FE -59

1.O1E+07 1.OE+08 1O0E+09 1.OE+10 -- -A-- -35

Time after final shutdown(sec) -- ZR -93

Inboard VV inner wall-2 (analysis point -9)

-ALLinduced activity (r=365.3cm)

-- .- -55

1.OOE+1 1 - -CO - 0

l O- 57

o -*--~~~~~~~~~~~~~~~~~~~~MO -93

-f---NI 59

,1.OO1E+05 ------ --f- -NB- 49

-4~~~~~~~~~~~~~~~~~~~~~~

1.00EA3 --------- ~ ~ ~ ~ ~ -4- C -S

1OO0E+OO--

1.00EA0 ----- -...-- N- 1

1 .OOE-01 -- X N-5

1.OE+07 1.OE+08 LOE+09 LOE+10 --- - E -59

Time after final shutdown(sec) ---&--S 35

Inboard blanket shield-I1 (analysis point - 10)

- 52 -

JAERI-Tech 2002-083

induced activity (r=395.45cm) - L-- E- 55

1.OOE+ 1 3 ~ ~ ~ ~ ~ ~ ~ ~ --- CO 60

1.00E+12 ~ ~ ~ ~ ~ ~ ~~~~~--N -63

-4-MN 54

--- CO -57

---MO 93

0 E -4--NI---59

11.OOE+013 -- NB 93m

> --- Q~~~~~~~~~~~~~~~~~~~~~~~~~~- 49

.g1.OOE+05C ---~~~~~~~~~~~~~~~~~~~~A- NB 94

1.OOE+04 ..;(- X-- 9 -4- TC -99

1.00E+03 ~ ~ ~ ~ ~ ~ ~~~~~--- CO -

1.00EA1 ~ ~ ~ ~ ~ ~ ~~~~~~--I-MN -53

1.O1E±07 1.OE+08 1.OE+09 1.OE1+1O0 - FE 59

Time after final shutdown(sec) .. ---- S -35

Inboard blanket shield-2 (analysis point -Il)

induced activity (r-85 1.55cm) --- L

-----h-FE 55VOO1E+1 3

-- CO -60

1.OOE+1 2 --- - ---- N 63

1.OO -11-- -.-........ ---4--MN -54

Li -E---~~~~~~~~~~~~MO 93'f1.OOE-409-

~~, 1OOE+08 -- -- - ~~~~~~~~~~~-0--N I 59

1OO1E-i08 - - ------- 4

1.OOE+06 -- C -14

1.OOE-i05 ---- 4-H - 3

10E+04 N-- BA- O94-A-A-&---A - A----~~~~ --4m--TC-99

1.00E-i03 ---- COS

--- ~- --a---X- NB -91

1.O1E+07 LOE-i08 1.OE-i9 1 OE-.1 --Q FE -59

Time after final shutdown(sec) S---35

Outboard blanket shield-I1 (analysis point -12)

- 53 -

JAERI-Tech 2002-083

induced activity (r=882.03cm) -ALL- -55

1.OOE+1 1 -*C - 0

---MN -54

O- 57

U ~~~~~~~~~~~~~~~~~-I*-MO -93

~,1.OOE+07 NI- 14

1.00E+06 ------ - - -- NB -93

1.0OE-O1 ---- V 4N-9

1.O1.0 E+0 C.EO .E0 .E1 -- 14-5

Time after final shutdown~~~sec) --- A- N5 -54

TC- so1.01DE+01 -- ----- ~~~~-6-NI-6

1.00EA0 ~~~~~~~~~~~~~----O N-57

1.0OE-01 ~~~~~~~~~~~---- M -3

1 OOEA7 10A .0E ---0-NI -59

----------- ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ --- H

-1Outoad lake hild2 anlsi pin -3

1.OOE+10OOO-6

1. E+0 NO-i0 -630 OE1

54~~~~~~~~~~0M 5

JAERI-Tech 2002-083.

induced activity (r=895.2cm) - L-- - E- 55

1 .OOE+09 --- CO -60

1.OOE+08 ---------- ~ ~ -U- NI -63

6 N- 541.OOE+07- -- - -- - - -

3 CO- 57

1.00IE+06 0 ~~~~~~~~U-MO -93

1.OOE+05 ~ ~ ~ ~ ~ ~ ~ ~~~--NI - 5 9

11.OOE-i04 - -- - ---- B 93S ~~~~~~~~~~~~~---V -49

U %_ 6 ~~~~~~~~~~-- C -14

A -t- ~:~ :\:~-4---H - 3

1.00E+01 :.a fLU. -

- ---- 1--'~~~~--~-~~--m--------X---TC -9 9

----- CO -58

--- X--- N8-91

1.00E-02 ... ...... -o --- x---MN-53

1.00IE-03 ~~~~~~~~~~~~---Q---FE -9

11O0E-i07 l.OE1+08 1.OE+09 1.OE+1O - S -35

Time after final shutdown(sec) -- 9 3

Outboard VV inner wall-2 (analysis point - 15)

-ALLinduced activity (r=959.2cm) FE -

10E+05 -- CO- 0

U-NI 631O0OE+04 - --- -i- - -- -

* . ---~~~~~~~~0MN 54

1.OOE+03; m CO--5

M -MO 931. DE+02 .....

N0---59

1.OOE+01 6N 3

S E ~~~~~~~~~~~--V -491.0OE+O :..---C 1

C~~~~~~~~~~~~~~~~~~~~~~~~~~~6C1

1.00IE-01 ----------- ... 3-U--IC-9

1.OOE-03 ....-...... 4--- CO -58

.-----MN- 53

1 .OOE-05 --- *---FE -59

1.OE-i07 1O.E+08 1.OE+09 1.OE+10

Time after final shutdown(sec) ---- R9

Outboard VV outer wall- (analysis point - 16)

- 55 -

JAERI-Tech 2002-083

induced activity (r.964.2cm) -ALL

-55

-ACO - 0

1.OOE+03 ~ ~ ~ ~ ~ ~ ~ ~~~--MN -54

1.00E+02 M CO ~~~~~~~~~~~~~~~- 57

1.OOE+01 0~~~~~~~~~~- - MO -93

~ 1.00E+00 -- NI -.

--- ----- & ~~~~~~~A- NB -93m

21 ~~~~~~~~~~~~~---V -49

--.- X....A-N --- -C14

1OOE-03 ---- *---*--h-- - -£--£--

1.00E-04 --- 1----------NB -94

1.OODE-05 -- 11--- - TC -99

1.OOE-06 ~ ~ ~ ~ ~ ~ ~~~~~-4-CO -58

--- X- NB -911 .01DE-07

--1- MN -531.OOE-08

--0-FE -591.OE-i07 LOE-i08 1.OE±09 1.OE+10

--- A--S 35Time after final shutdown(sec)

Outboard VV outer wall-2 (analysis point - 17)

-- -- LLinduced activity (r- 1 030.42cm) FE- 55

1.01DE+06 ~ ~ ~ ~ ~ ~ ~ ~ -ACO -50

1.00E+05 ~ ~ ~ ~ ~ ~ ~~~~--NI -53

MN-CO - 57

1.OOE+02 ~ ~ ~ ~ ~ ~ ~ ~~ N-MO -93

--0--N I -59

&N- 93m

-1--V -49

-O-C -14<1.OOE-02a .X

- --- - - -5 ---*-- H - 3

E-03 - :~~~ ::*::: :::~~~~ ---A-NEI-94

1.OOE-04~~~~~~~,--q-- --C -5

--40--TE-59

1.OE1+07 1 OE+08 1OE+09 1.OE+ 10 -- -S -35

lime after final shutdown(sec) -I-G ZR 93

Outboard TF coil casing-I1 (analysis point -18)

- 56 -

JAERI-Tech 2002-083

induced activity (r- 1041.8 cm) -ALL-- -55

-- CO -60

1.00IE+03, 0 ~~~~~~-4MN - 54

-N-CO -57

1.OOE+02 0 MO ~~~~~~~~~~~~~~- 93

1.0011+01 --------------- ~~~~~~~59N- 93m

1.00IE+00 10 v ~~~~~~~~~~~~~~~~~~~- 49

<u 1.OOE-01 ----- ------ C -14

w --4--~~~~~~~~~~~~~~~~~~H - 3

U 1.O0OE-02 --- r------- -- K -4-TC9

1.OOE-04 ~- ~~~~~~ * - * ~~~~~~--- X-NIB-91

1.00IE-06 G~~~~~~~~~~-4- FE -59

LOE+07 1.O1E-i08 1.O1E+09 11O0E+1 O[_1

Time after final shutdown(sec) Z-93

Outboard TF coil casing-2 (analysis point - 19)

induced activity (r-1 101.51cm) W L

E- 55

-- CO -60

---- NI 63

1.OOE+01 o ~~~~~~~4-MN 54

1.001E+00 ----- X ~~~~~N--CO 57

o -U---~~~~~~~~~~ MO 93

cr 1.OOE-01 -0--------- -- 4-NI -59

-6-NB -93m

--f -V 49

<1 11.0OE-03 0 ~~~~~~-4-C -14

C ---A-- ~~~~~~~~~~~~~~~~~~~~NB -94LOCIE-05 X. ~~~~~~~~~----TC -99

1. U--06 -------- ---- O S

1.OOE-07 ---.-- 4----U----u -e-- ---X-- NB -91

L.OE+07 1.O1E-i08 1.O1E-i09 1.O1E+] --- 0-- FE -59

Time after final shutdown(sec) - - S -35

Outboard TF coil casing-3 (analysis point -20)

- 57 -

JAERI-Tech 002-083

induced activity (r= 1 1 11.86cm)LL---- FE 55

-- CO - 0

1.OOE+01 ~~~~~~~~~~---NI1 63

1.OOE+00 6 ~~~~~~~~0-MN -54

1.0OE-01 % CO ~~~~~~~~~~~~~~- 57

-46-MO 93

fi --04--NI- 59

21 ~ ~ ~ ~ ~~~~~~~~~~~--NB -93m

z; 1.OOE-04 --- -- - -49

1. -E4-5C -14

C-) E*- $A-- H -3

--- A- NB -941.OOE-07 ------- X--- -5-

1.OOE-08 2* -

---X- NB -91

1O0E+07 LOE+08 LOE+09 1.OE+1O0 --- FE -59

lime after final shutdown(sec) --- -A- -3

Outboard TF coil casing-4 (analysis point -2 1)

- 58-

JAERI-Tech 2002-083

Appendix-2

Clearance indices for TF coil casing, VV and blanket

- 59 -

This is a blank page.

JAERI Tech 2002-03

Araysis pnt: Surfaceno CS ccil case

),,bold Region 1 ~~~~OtbordRegion

10 I-O~~~~~otO~----0 Nb-91

2 10~~~~~~~~~~~--t 115 90 0 ..... . .......... 1 3 - oa

-w iot.~~~~-0-Ni6

4 ' . .. . . . . . . . . . . . .. . . . . . . . . . . . . . . . .

on......w...... ...... ........... ....

W1 0- .. . . .. . ... . .. .

W 1

o< 11 0 ......

10 .. ... 20 40 60 80.................... . 100....

lim after-fina shudow -(yar

101 ~ ~ ~ ~ ~ ......... - -- -5 -- ------ ---

12

0 20 40 60 80 100

Time after final shutdown (year)

~~~~Clearance index of inordT coil casing (oergo Sci ie

Amyssdn:Sra~olrmrTcclas~nsree- ~c61ie

JAERI-Tech 2002 083

Asalysis p nt: Surfaced lxamrdTF ccii cease( repom)

Inboard IZ~~gion I OuitLx>4 > Region

10- ~ ~ ~ ~ ~ --- C1

i on .............. .......

0

to 0 - -.....10'~~~~~~~~~~~~~~~.................

0 060 8

aftr..na.sutown.. ar

ClaacX ne fibadT olcsn ns ein

Analysi ..nt:S .fac I ....d c. lcas).e. wll..CSc.

1 0 rf-----1

T 10-f4--N0 6310

I bad e.o 0.tmr eio

40 10,

CS ~~~~~~~- eS

o 10 ~~~~~~~- 3 - oaI- -~~~~~~~~~~~~~~~~~~~~~

'c

in 1

1 0-2 ------s

10O

0 0 40 60 80 tOO

Time after final shutdown (year)

Clearance index of inboard IT coil casing (inner wall /CS coil side)

- 62-

JAERI-Tech 2002 083

AMulysiu ou(: Surface of ircrTF wI case (asmna si®~

Inboard tRegion IOutkba rd Region

10,

10, ............. . .. ......... 0-- 1

1 0 ... .................... --0- -C-GO --sa- - C 9910 ~~~~-V0--NI-GO -- Totai

W3 10 ... .. ...

W 1 0 ..............

0 ......... ...

0.10...

1 LEFe 1--

1 0'70 20 40 60 80 100

Timne after f inal shutdown (year)

Clearance index of inboard TE coil casing (plasma side)

MA yiu pint: Surface d lnbxard W Outer sfd (CS cal side

Inboard R,.oon ~~~~~~~Outboard Region

00

0 20 40 ~~~~-0 -C60 110 1009

101 --Ni-663

JAERI Tech 2002 083

NAmysis prnt: Srf aceof W uier s~d (1asmasi d)

Inboat di Region Outboard Region

-Ni-63 1Total

<, 10O

70

O 1

I-I

0 20 40 60 80 100

Ttme after shutdown (year)

Clearance index of inboaid VV outer shell (plasma side)

kalysis pint:StrfaceotfWire shdl (CScil side

Inboard Region ItifadRegion

10o

101 .............. I- t 60b --E- -b941

I---MnS3 TohSE

-j I-D ~~~~~~~~~Ni-63

0

ci 10O .......<

0 20 4 60 0 0

1o~ t 2%-.64 -.

JAERI-Tech 2002 083

Amayi ian: Surfac ofW iran s~ Oras i deo)

Inboard ORgio o ubr i e

~ 1o~ '~) . flt %n~t ?0-.

0 1

0 20 40 60...... . .......... ... 00. .

1 c), ~ Tm atrfia hudw (er

Cleaanc inexo. ibor.V.inr.hel(pdsasie

-J0-

020 4 0 8 0

10,

~~~~ 10 I..~~~~~0--CO6 -5--b9

10 .......

1003 20...40 ..0...... 0

iq~~~~~~im fe ia sudw er

Claac<nexo norolaktsil2(Sci ie

W ....~~6 ........

JAERI-Tech 2002 083

AroysS p Inl Strface of Blarket Sredd( Oasma sice)

111900 rot Region ~ ~ ~ ~ Oitl~ir Roo

10..

10 -0 CobS ~~-U-c-SI--H-3 - Total

C) ) -0 - i6

Iii.. . . . ... . . . . . . . .. . . . . . . .

0 1 . . . . . . .. . .. . . . .. . . .. . . . . .. .

W0

0 20... ...0 . 608.0

........... Tim e afte ........ ...utdow n .(year)

Clerane index of inbardblnke.siel .(pasa.sde

1 20-0--60 -U--Nb-9Tim ate --na sutow (4ye-a r

MIn

1~~~~~~~~~~~~~~~~~~) ~ ~ ~ ~ ~ ~ ~

Tim ate fnasutow (year)

Cleaanc index of....... oubor. bane.sied(pasasie

1 I .... ...... ..... ......... ...6 6....

JAER1-Tcch 2002%083

Am lss pm t. So.(ace of Blar~oet Shidd] o ryost side)

Intmaud Region 1 ~~~~~Ouitboard Region

10 ~~~~~~~~~~-0. b9-0n-54 -- O-99

10? -... ...... 54 .- Tl0 N- 6

W 100'.....-.............

o I. . . .. . . ... .. . . . . ... ..

10

1 01, .

0 20 40 60 80 100

Time after final shutdown (year)

Clearance index of outboard blanket shield (ryostat side)

Aidysispdcst: Surface - Winnurscll(plasma sicvŽ)

In~~~oard Region 0.~~~~~Qtftosrd Region

1 o7

--0-- Co-6O --WN-94--l--iGO --A-f 99

-j 101

0 1O1 .... - -0 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __... ... ... .. _ _.. ... ..

o o0-U - ...... . .......

i- Of

1 xx 10 ........ .. ...... ..... .. ..... .......

C)

1 0-

0 20 40 60 80 100

Timne after final shutdown (year)

Clearance index of outboard VV inner shell (plasma side)

- 67

JAERI-Tech 2002-083

Anaysts ptnt : ur face d W irmns fI( cyotatI uicL)

0

tnloa rut Region I Outboard Region

>u 10 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~~~~~~~~C 1 in:... ............. o 6 b 9

0 20 40 tOO 80 100~~~TC-9

0>4.. . .. ... .. .. 0.

10 -O 60 -U--Nb.....4

> 10-

0 20 40 60 80 100

Time after final hutduwn (year)

Clearance index of outboard VV outer shell (laosma side)

A68i it uraeo otrsW Osasc.

JAERI-Tech 2002 083

Anaolysis pnt: Surfaceocf Wouaer-d w (crycatat sidef)

Inboa rd Regi on IOtb oard Region

. . ---- ~~~~~~~Fe 55 --0--C1 1410 --0-......... -n60 -- NS 94

-~~~~~ 1 - X~~~~~~~~H-I- - Totali 10 .. .......... --.. -. Ni-en6

0

F-

Wj 10O .. ... ...

C o a - -

1 O'0 20 40 60 80 100

Timne alter final shutdown (year)

Clearance index of outboard VV outer shell (cryostat side)

Arnysispxint: Surface of irra TFcl case

Inboard Region IOutlrard Region

4O. ............... es --0--c 1A10 ~~~~~~~Mn-54 -- N-94

3 . -0 -~~~~~~~~~~Co-hO --a-C 9910 ~~~-f - Ni-63 -TntaI X -~~~H-3

o 2-j 10 ..............

xo c-

~~~~~~~~~~~~~~~~~. . . .. . . . .. . .- . . . . . . . .

1000 20 40 60 80 100

1Tiwo after final shutdown (year)

Clearance index of outboard TF coil casing (inner wall /plasma side)

-69 -

JAET-Tech 2002-083

Analysis pint: Siufaed iaer TF ccil case ( cryes at side)

Inboard Region IOutboard Region

102 -0--~~~~~~~~~~Co-60O N 9U-164-~A- Mo 54 -a- r99

~~ 101 X::H~~~~~~~~~~3 -Oc~~~Ttal

0

1 -i 1

0) -s~~~~~~~~~~------- ---

-D 10

0 20 4 0¾ 0

Time after final shutdown (year)

Clearance index of outboard TF coil casing (inner wall /cryostat side))

Analysis ant: Sfaceef cute TF cI casea(plasmasi®~

Inboi uboard Region 0toFtzgo

0 0,55 --0 ---- fe-H 310 .............. Mn 54 -U]--Nb-94

o . . I~~~~~~--X--C-1 41-

o 510 .... .....

F- ~~~~~-101

0 20 4 60 0 0

10 ~ ~ ~ 7

JAERI-Tech 2002 083

Argiysis prnt: Stirface of cuter iT cal case ( cryotat sid)

fnhcoard [fcRofl0,tx~tdRgo

102

C) . 20...... 40....... .08...00Tieafe fina -hut on -(year)

Clearance index of outboard TF~~-L coM cSing (oute wal/cysttsd)

10 1 ...... ......... .... H 71t1

This is a blank page.

JAERI-Tech 2002-083

Appendix-3

Classification of solid radwaste

- 73 -

This is a blank page.

JAERI-Tech 2002-083

Classification of radwaste for its safe disposal in Japan

Prepared by Takeshi Maruo (JAERI)

November 24, 2001

In japan, radioactive solid wastes are classified for regulatory purposes as follows:

* High level radwaste (HLW):

"HLW refers to the radioactive waste, which comes out from the reprocessing of

nuclear fuel. This is very rich in alpha emitters as well as beta gamma emitters.

The geological disposal (a few hundred meter deep underground) with natural and

artificial barriers is required of HLW for regulation;

* Low level radwaste (LLW):

Japanese regulation requires that LLW shall be classified into any of three classes

shown in TABLE-i and shall be disposed in accordance with the approach specified

to the class. In addition, activated waste is categorized into LLW

TABLE-i: Classification of LLW nd approaches for the final disposal in japanClass Criteria for classification Approach for the final disposal

(Bg/ton)Li waste H-3: C Ž 50P** Burial in several ten meter deep underground with

C-14: C Ž 37G* artificial barriers (concrete pit or more effectiveK-40: C Ž 170M** structure).Ca-41: C Ž 3.1G*Co-60: C Ž 11.1T* The depth shall be determined appropriately based onNi-63: C Ž~ 1.11T* evaluation as for radiation exposure resulted fromSr-90: C Ž 74G* extremely unlikely events (radiation exposure up to a

Nb-94: C 1G** few ten micro-Sv/event can be approved for anTc-99: C Ž 190M** extremely unlikely event).Cs-137: C Žt 1.l1T*Eu-152: C Ž 360M*

an alpha emitter: < 1.l11G'L2 waste H-3: 3.0G* < C < 150P** Burial in approx. 10 m deep underground with artificial

C- 14: 1 10M* • C < 37G* barriers (concrete pit and a clayey soil layer).

Ca-41: 150M* • C < 3.1 G*Co-60: 8.1G* t• C < 1.1T*Ni-63: 7.2G* < C < 1.11T*Sr-90: 4.7M'* < C < 74G*

Nb-94: 18M** < C < 1 IG**Tc-99:9.OM** < C < 190M**Cs-137: IOOM*: <C < 1.11T*

Eu-152: C < 360M*an alpha emitter: C < 1.11G*

L3 waste H-3: C < 3.OG *Burial in near surface (a few meter deep) underground_________ _______________________without artificial barriers

- 75 -

JAERI-Tech 2002-083

C-14: C < 11OM*Ca-41: C < 150M*Co-60: C < 8.1C*Ni-63: C < 7.2G*Sr-90: C < 47M*

Nb-94: C < 18M**Tc-99: C < 9.OM***Cs-137: C < 100M*Eu-152: C < 360M*

________ an alpha emitter:C_<_17M* ______________________Note "C" means concentration of radioactivity in waste.

M =le+06, G =le+09, T =le+12, P =le+15, E le+18A value with a single star-mark (*) is quoted from the Article 13-9 of the governmentcabinet No. 324 for "the law for regulation of nuclear source material, nuclear fuelmaterial and reactors".A value with a double star-mark (**) is not enacted yet, but it is used in the examinationof safety approaches for radwaste disposal that the government has held. The value issuch that can bring 10 micro-Sv/y to a member of the public after 300 years fromdisposal. All the credible pathways of internal and external exposures due to release fromnuclear regulation on radwaste are considered in the evaluation.

During regulatory control (<300 - 400 years), radiation exposures of a member of the

public shall be maintained ALARA by radiation shield; prevention of human access to

the waste; and monitoring of radiation and radioactive materials in the environment.

A target value of 100 micro-Sv/y is recognized appropriate for ALARA.

After the control duration, internal and external exposure from all the credible radiation

exposure pathways due to buried waste must be less than 10 micro-Sv/y or a few ten

micro-Sv/ event.

- 76 -

JAERI-Tech 2002-083

Appendix-4

1. L2 limit indices for major tokamak components

2. L3 limit indices for major tokamak components

- 77 -

This is a blank page.

JAERI-Tech 2002-083

1. L2 limit indices for major tokamak components

1 0-L2 wn* indx for H-3is below 1O0 at final shutdown.

U-X-Ni3

7 I Tc99I

10 I.~~----- - :--

2 10 4 I~~~~~~-- - ------ -

10~~~

0 20 40 60 80 100

Time after final shutdown (year)

L2 limit index for surface of CS coil casing

10 ,.Y-- H-

0~~~~~~~~o6

-8

12

13~~~~~~0

0 20............40...... ...... 0...... 8 0........ . 1 00........

10 -1 ............... T im e after...... final..... sh td w (year)....... ..........

L2 limi indexfor inbard TFcoil caing (nsergo/CScisd)

12 ~ ~ - 7

JAERI-Tech 2002-083

1 0-eL2 flin-ndexfor H-s is below 1 0 -atfna sud.X

-3 ~~~~~~~~~----c4

4 ~~~~~~~~~~~~~~Total

44 ~ ~ a--

-6 ............. .... .....

---V - Y--~~~........................ ..........

10-7

0 20 40 60 80 100

.Time after final shutdown (year)

[2 limit index for inboard TF coil casing (nose region /plasma side)

1 0-4

Ljimtidex for H-3 bsbelowl10 <at fnai ShUtdown--X--H-3

- ~~~--O)--C-141O ........................................... --0 -- Co-6O

10 -. ~~~~~~~~~~~Ni-6310~~~~6 L::1i~~~~~~N-9

10 -- --

10~ ~ ~

10

0 20 40 60 80 100

Time after final shutdown (year)

[2 limit index for inboard TF coil casing (inner wall / CS coil side)

80s -

JAERI-Tech 2002-083

1-2

U2 limit idex for H-3 is below 10 --at finaJ shutdown.

-0*--Co 60-U--" Ni63*

I-V-Nb 941

4 ~ ~ ~~~~~~~~~~-- Tot99

-J ~~~~C~

1 0

0 20 40 80 80 100

Time after final shutdown (year)

L2 limit index for inboard TF coil casing (inner wall /plasma side)

10-1Ui in* idex for H-3 is below 1 0 a k hton

-U--Ni-63

* I~~-Y--Nb-94Ia~~~~~c io~~~~~~~~~~~ - - --t 99

3 ... ... ... ... ... ..S... ... ..

CA 10 f 0 -

.6

10 8

0 20 40 60 80 100

Time after final shutdown (year)

L2 limit index for inboard VV shell (outer wall / CS coil side)

-81 -

JAERI-Tech 2002-083

0-1 . . . --

[zl"--ex for H-3 is below 1 8afra shutow I'

- -- X--H-3--- C 14

-210 ........ . -Q -CO-60O .-U Ni63-W--Nb 94

10 . .......... otA

-- 4

-J --- 0 0- 0~~~~~~~~~~---- - -------

1 0

-7

0 20 40 60 80 100

Timne after final shutdown (year)

L2 limit index for inboard VV shell (outer wall / plasma side)

[2 limit kxix for W-3 is below 10' ̀at fialshtdown. -0--C-1 4- . ~~~~--0- Co-60

10 .............. .......................... --Y -- Nb-94--A&--Tc-99

-Totil

10O -

1 00

1 0,

0 20 40 60 80 100

Time after final shutdown (year)

L2 limit index for inboard VV shell (inner wall / CS coil side)

- 82 -

JAERI-Tech 2002-083

101H3sbow[2 [irtt index fo sblw1 0 at final shutdown.

-O--14-0--Co 60

-A^-- Tc99

~~~~ -t~~~~ ---

X ----------2 -- -- '- - -…-------- 1 ... ....... ......... .... ........ .. ......... ......... .

-J Z24.. 4~~~~~~~~~~~~~~- -y. O---

3~~~

1 0-6~ ~ ~ ~ ~ ~~0

0 2 0 4 0 6 0 8 0 100

Time after final shutdown (year)

[2 limit index for inboard VV shell (inner wall / plasma side)

0

-0-C-14

1 ......... E Ni-6310 ~ ~ ~ ~~ ~.............:........... ....... - Nb-94

-A,-- Tc-99

-2

---- A- ----A-~~~~~~~~ - '- ---

-40

-6

10~

0 20 40 60 80 100

Time after final shutdown (year)

[2 limit index for inboard blanket shield (rear surface)

- 83 -

JAERI-Tech 2002-083

02

0C141

10 ........ ........................... lM -N i6311-- Y-Nb 94

c-o99-Totalo

10 ..............

(4 10*

-4

100 2 0 4 0 60 8 0 100

Time after final shutdown (year)

L,2 limit index for inboard blanket shield (front surface)

1 0 -

-- X'--Nb-4-TC-4

9- N-4

10

10 ....... .

X~~~~--s ____ ______ ____ ............. __ _______-- - - - - - - - ___L ______-- - - - - ___L- - - - - - -_

1 0 ...20.40 ...... 0..... ....... 0..... 100........

2~~~~~ieatrfia hton(er

L2 limit ....index .. fo outboard... blanket.... shel. (rntsufae

3 ~ ~ ~ -8

JAERI-Tech 2002-083

100 ~~~~~1 ~ ~ ~ --X-.H-3

--O--C-60

--U-- Ni-6310' ................................. -- V -- Nb-94

-d- Tc-99-Total

10 ---- ---

107

0 20 40 60 80 100

Time after final shutdown (year)

L2 limit index for outboard blanket shield (rear surface)

101 L24- xfor H-3 is below 1 0 -'at thMa shtftdo 2J [-X 7 T ]

I.0--C-14U

10

10-- - -- -- -- --- ---

x --- & 6 6~~~~~~-- -- -. - - -

-3

C14 10 ~ ~

10

020 460 8 0

Time after final shutdown (year)

[2 limit index for outboard VV shell (inner wall / plasma side)

-85 -

JAERI-Tech 2002-083

10 0 1 . . . 1 . r . . -X -

10 lmtidxfrH3 sblw1 a ia sudw. - -- C

-7

0 -20 ----- -40 -0 8 100

1 U4

L2tittiexforH-3isbelowlO"atfinalshtdwn.

-U- -N1 63

-s - ~~~~~~~~~~~~~~~~Total

ri 10 ......

a a I .... a~~~ ~~....... ...... .L...........

0 20 40 60 80 100

Time after final shutdown (year)

[2 limit index for outboard VV shell (outer wall / plasma side)

-86 -

J AERI-Tech 2002-083

-s _____________________________________X____H___3

108-OC1

1 ~ ~ ~ ~ ~ ~~~~~~-7-06

-9~ ~ ~ ~~~~~~~~~~b96 1 0 . . . .. .. .. . . ... . ... .. .. . . .. . .. .... .. . . . . .To a

-7

Ilk~~~~~~~~~~~~~~~~~'

12

0 20 40 60 80 100

Time after final shutdown (year)

L2 limit index for outboard VV shell (outer wall /cryostat side)

iiindex for -ismo1O 1 2--at f ii& shutdon 0 -Cj

0 o- o-G

106 -&.-~~~~~~~~~~~~~~~~~~T c -9 9

1 0r

S 0

10

1 0 ~ ~ ~ ~ ~ ~~~0

0 20 40 60 80 100

Time after final shutdown (year)

[2 limit index for outboard TF coil casing (inner wall / plasma side)

- 87 -

JAERI-Tech 2002-083

[2 ijt nx for H-3 is below 10__at fialshutdon' --O:-C- 14-.-- Co-GO

-6 -U~~~~~~~~~~~~~~~- Ni-G 310- .................. -- Nb-94

-A- - Tc-99-Totad

10 .......

82 1 0 ...... 0--......................

10

1012- ~ ............ .... J ...... .. .... ..... ................

0 20 4 0 60 80 100

Time after final shutdown (year)

L2 limit index for outboard TF coil casing (inner wall /cryostat side)

jjliitiex for H- 3 is below 1 0 - at final shutdon. - XH-3*-0-C-14

* --0-Co-GO-8 ....................................... -U -- N i-63

--- -Nb-94

-&6-Tc-99- ~~~~Total

-91 0 -...... U

--- 0 … 0----------

1 0

--- 4-…A- -- '~~~~~~---- i-- ----

-12

13

a aa......... ..... ................ . ............. iAO . .. ......

0 20 40 60 80 100

Time after final shutdown (year)

[2 limit index for outboard F coil casing (outer wall/ plasma side)

- 88-

JAERI-Tech 2002-083

L2Iimitiindex for H3 irsbelow 10alo shtor --X .H 3-0- C 14

10 .. ............................ ...... -- Ni631

--- Tc-99

Total

1 0 --........y-h---- Y----------…-

-~~~~~~~ -12 ~ ~ ~ ~ ~ - --- - -

10 C

1 3

10 1 ± L 1 1 I LL...............L...............

89 -

JAERI-Tech 2002-083

2. L3 limit indices for major tokamak components

-3

--X- -H-3-- 0- -C-14

4 ~ ~ ~ ~ -- Co-6O-4M- -Na-63..

--- Nb-94-A-- Te-99

- - ~~Total

10 .. .......

6 -- - - - - - - --~~~M 1 .. ...... ... .. ... .. ... ... ... . .... ... .. ...... . .... ... ... .. ... .. ... ... ... ....

7~~~~~~~~~~~~~~~~~~~~~C'

1 0 ........... ............... ............... .. ................. ...............

020 460 810

9 ......... Time..after fina]...shutdown.... (year) .......

[3 limit indexTfor sufae f soil cyasin

--X- -H-3-- 0- -C-1 4

4 -4 Co-Go10 - ~~~~~~~~~~~~~~~~~~~~~~~~--U- -Ni-63..

--- Nb-94-- a- -Tc-99

-TotNl

10 *bf e

i~~~e C.

10

t~) 10

~- 906

JAERI-Tech 2002-083

1 0-2~~ ~X~N3

--0- -C-14

-3 -- Y- -Nb-94-- ah- -Tc-99

-Total

-410 I..t......... ... - - . ....

"fl~~~~~~~~~~~~~~~l

-6

10 - .. I 6

10 L.LJ.1..~~~~...L................................0 20 40 60 80~~~~~-6 100-6

10 ~~~~r~~r -i~~~*w- T .c-9

100

-3~~~~~~~~~~~4

10 -

x . ~ ~ ~ ~ 9-1*

JAERI-Tech 2002-083

10 -- 1 -r rr

I- -O--14

-4 -Ni-63

H-W- -Nb 94

10

cn 10 ......

10-

0 20 40 60 80 100

Time after final shutdown (year)

L3 limit index for inboard IF coil casing (inner wall /plasma side)

10

10 ............. Co 60U -- N;-63

- -- Nb 94--&--Tc 99

10 -Total.........

x 0 - 1z ......

X..

-0-

10 20 4 6. 0

Tim aferfinl hutow (yar

L3 imt nde fr nbordVVshel ouer al /CS oi sde

-s ~ ~ -9

JAERI-Tech 2002-083

10 Tt

--- 0~~~~ ~O- 0--1

0~~~~~~~~0

b-s~~~~~~~~~ -- b9

T~~~~~oa10 ................ ....................... H 3.

X ~ ~ ~ ~ ~ ~ ~ ~ ~~~I--C1

L--------4 --Ni -63 --

4~~~~~~~~~~~~~b9

1061 Tt

--- 0 3

02h

0~~~~~~~~~0

10 20.40.60.8 100........

1 .... . ..... Time. after final...... shutown.year

L3lii ide oribordV sel ine wlliCScolsie

2~~~-9

JAERI-Tech 2002-083

1 0 3~~~~~~~~~~K--

- -X-H-3 2 1~~~~~~~-O-C1l

10 ......... 1 -U - N 630

a A-Tc-99

101 ~~~~~~~~~~~~~~~~~Total

oJ010 .nr - ~ - a

~~--yb hey.. ~---------

-2-

10O

0 20 40 60 80 100

Time after final shutdown (year)

[3 limit index for inboard VV shell (inner wall /plasma side)

3 ~ ~ ~ ~ ~ ~ ~ ~ - - -

-o 1 *1'~~~~~~~- -C1

0 20.40..0..0.10

K ~ ~ ~ ~ ~~~Tm atrfia hudw (year)i----

L3 limt.ndx.orinoad.banetshel.(ea surface)...

.. ... . ... .. . 4.. . .. . .. . .

JAERI-Tech 2002-083

10 ..... .... ........... ......... ........ ho 6

-- --Ni6

1 0~~~~~~~~0

101

S~~~~~~~~~~~~

10

en 1~~~0 2 06 0

1o05

-1.

- 95 - ~ ~ - W--Nb9

JAERI-Tech 2002-083

03

--X--H-3-O--C-14

2 -0*--C-GO10 ........... .............. G.....

-V Nb-94- - ~~~~~~~-- -Tc-99

1 - ~~~~~~~~~~~~~~~~~Total

10

0-3~ ~ ~ K

en 10

020 460 8 0

Time after final shutdown (year)

[3 limit index for outboard blanket shield (rear surface)

10~ 3

-0 -C 4-0- -Co-GO

--A- -Tc-9 9-Total

10 -- ..-... .. ..........

--

10~~x 0 4 0 8 0

100 . 9 ~~~~im af ina hud- (er

L liit inex-fo oubor VVsel(nnrwl- pam ie

---a - 96

JAERIPTech 2002-083

2 .. ........ 2....................... .... l--O -C14 I ..10 I~~~~~~~--0-Co6O

- -3--Ni-63

101 -- Total

1 0

10 ............ ... .... ........... ....

4~ ~~~~~

1 0

0 20 40 60 80 100

Time after f inal shutdown (year)

L3 limit index for outboard VV shell (inner wall / cryostat side)

10 rI- r

10 Jj1..........-O--C14 ...

1O Co 60*-E-Ni-63

10 ~~~~~~~~~~~~~~~~~~Total

4.0) -

- ---U% -- ~~~~~~~~O~--…-

1 U6 '413w~~~~~r-- - -- ~6-- --- r-- - -

1 0 0. '

0 20 40 60 80 100

Time after final shutdown (year)

L3 limit index for outboard VV shell (outer wall / plasma side)

- 97 -

JAER1-Tech 2002-083

1 0-

-3 ~ ~ ~ ~ ~ ~ ~ ~ - - -10 ......... ................... .... O C 1

-40 0 ... 40.. ...... 0..... ...... 0..... 100.........

Tie ferfia suton yer

10 L-L --- L-2--U-- i630 20 40 60 80~~~~~~N 94 0

Tim ate fna 1 2htdwn(yar

L3 imi idexforouboad Wshll outr a-lcosta ie

en 10 ..2,

10~~~~~~~~~~~~~~C1

4 TotaTieafe fnl htdw (er

-7~ ~~-9

JAERI-Tech 2002-083

-2 _______________

VY--Nb 943---- Tc 99

-4~~b-

0.

0 20.0...80 10

Time after final shutdown (year)

L3 limit index for outboard IF coil casing (inner wall / cryostat side)

10 -5T I u-r-X-H-3

0 *-Co-6O

-6 ~~~~~~~- -Nb-94-h -Tc-99

Total

-710 .... - - - -

-8 -~~~~~~~~~~~~~~~~ I.- - ...........

10 ...... i............ ..........

10 ~ '~

101 .............

0 20 40 60 80 100

Time after final shutdown (year)

L3 limit index for outboard TF coil casing (outer wall /plasma side)

99

JAERI-Tech 200241083

10 J r I-- 1-- -X- -H- 3--O-C-14--0- -Co-6O

'a - ~~~~~~~~~~~~~~~Total

--- ---w-- -------

10 X

-x~~~~~~~~Z

1013

0 20 40 60 80 100

Time after final shutdown (year)

L3 limit index for outboard TF coil casing (outer wall / cryostat side)

- 100-

R#Otl (S1) (~fi

mi a2 sIJ2 tt soA a

Lit S A - I- A~L' m 5 E.R!, HEl m, h. d 10"8 x 97 -I EA 3 'F ikg fi ¼ ¼ ¾ " 0 p~ 9

as as U -~~~~ I' A SI. L 1012 'F T

t AL' V 7 K eV~ X 10' A t' m

Vt ~~~~ 3 A' ~~~ mel 10, 4 k

520 l~~~ ii7#S ~~ ed ¶0' ~7h h

W Vt 5 2 7 7~~ rad e - .602 18 x10-"J10 T t d

•0 44 Ph 2t5777 ~s r u =.66054 xWo27

kg 1W> 5' d

10'2 c)

~~3 ~fir7)t~~jbS1*flft${Ž 0 1Mifl '- n'9

l~~~~~~~I ~~~~~Hz a"- 10<'1 JX

I] ~~~~n F 7 N n~~~~~~~~g/s2 *~~~79 ' 7,hn]- A 0'

itt C '4 t & Pa N/r 2' - v b

t fL4,{*, M1 2 a A'J Nm A - AL bar

I . ¼4W 9k F W S HA' Gal V -5( DM V- W,[1M

1 5 9s - l C As 4 U - Ci Vt4 19854tPlflc1,tt5lVL{PWI . ~5t, hFAL V W/A p R'7 kJC 1 u DIAUCODATA 1986Fg3~

M 7~ 3 SV F C/V Sv rad LlcX :

ad ~ t - n( V/A Pt re rn 2. 4I1±VAt / hF 7-A 7 '9:1 9997 2- 2 S A/V

id 5S ' Wb Vs 1 A0. 1 nm"10<'m -a- 'tl-h t 7w7H5F -;$VttS )-CC

fa t 41 f t' Z T Wb/m2 ~of,1-M U CCI±4BLF:.

4 9' X '7U- H Wb/A 1 bar=0.1 MPa-1O'Pa 3. bar 4 1d, ~ l~tebktL, 7 1M a tA'9Z 'c

it ~ AL' - ./ 7 Im cd sr 1-alc-sS0m/' ~ 1IUl ~t~)-(T~tt) L, 97 A Ix Im/m

2I Ci= 3.7x 10"`Bq $

4. Ef $•8Z±ba.barn~i±~~4 ~~4 ~ N 9 L )L Bq s<1R=2.58x10-C/kg Ftio smm gt t•'

q& Ly *~~~~~ 3 9'P Gy S/kg I rad - cGy =10`Gy -1C Ahz t ' .

U - )L' Sv S/k~g l rem=l1cSv- lO2

Sv

itN(10'dyn) kgf fIbf it MPa(lO0bar) kgf/cm2

atm mmHg(Torr) bf/in2(psi)

0.101972 0.224809 1 10.1972 9.86923 7.50062 10' 145.038

9.80665 I 2.20462 ht 0.0980665 1 0.967841 735.559 14.2233

4.44822 0.453592 1 0.101325 1.03323 1 760 14.6959

Mt )l I Pa.s(N.s/m)=IPft7 X) (g/(cm.s)) 1.33322 xlO 1--1.35951 xIO<- 1.31579 x<10< 1 1.93368 x 10--

0M1tl I M2/s= I0'st( 27 F - 9Z)(CM,/S) 6.89476 x 10-- 7.03070 x 10`2 6.80460 x 10-2 51.7149 1

J(5= 10' erg) kgf m kW. h cal(tE ) Btu ft I bf eV I cal = 4.18605(434MV)

1 0.101972 2.77778 x 10-- 0.238889 9.47813 a 10-- 0.737562 6.24150 a 10" = 4.1845 (J4L

I 9.80665 1 2.72407 a 10-- 2.34270 9.29487 a 10` 7.23301 6.12 082 a 10" = 4.1855 J (1 5 'C)

4± 3.6 x 10' 3.67098 a 10' 1 8.59999 a 10' 3412.13 2.65522 a 106 2.246 94 a 1 02 = 4.18685 (J 2~

4.18605 0.426858 1. 16279 a 1 0< .65a0 3.08747 2.61272 x 10" {-4 r'S (At)

id 1055.06 107.586 2.93072 a 10-- 252.042 1 778.172 6.585 15 10` 75 kgfm/s

1.35582 0.1 38255 3.76616 a 10-' 0.323890 1.28506 10-- 1 8.46233 a 10'' 735.499 W

1.602 18 a IC"- 1.63377 a 10-<' 4.45050 a 10--- 3.82743 a 10`2 1.518 57 a 1 02` 1. 18171 a 0- 1

rA Bq ci u%4 G y rad 90 C/kg R 4Y Sv rem

1 2.70270ax10-'-- 1 100 1 3876 it 1100

3.7 a l0`' I 0.01 1 2.58 a 10', I 0.01

(86 I 12fM 26 H JA t)

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