japan atomic energy research institute
TRANSCRIPT
Japan Atomic Energy Research Institute
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(T319-H95
This report is issued irregularly.Inquiries about availability of the reports should be addressed to Research
Information Division, Department of Intellectual Resources, Japan Atomic EnergyResearch Institute, Tokai-mura, Naka-gun, Ibaraki-ken 319-1195, Japan.
© Japan Atomic Energy Research Institute, 2001
JAERI-Tech 2001-058
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JAERI-Tech 2001-058
Study on Residual Radioactive Inventory Estimation
in Reactor Decommissioning Program
(Contract Research)
Takenori SUKEGAWA, Mutsuo HATAKEYAMA+ and Satoshi YANAGIHARA
Department of Decommissioning and Waste Management
Tokai Research Establishment
Japan Atomic Energy Research Institute
Tokai-mura, Naka-gun, Ibaraki-ken
(Received July 18, 2001)
In general, neutron transport and activation calculation codes are
used for residual radioactive inventory estimation; however, it is
essential to verify calculations by measurement results because of
geometrical complexity of the reactor and so on. A methodological
study was made on radioactive inventory estimation in a reactor to be
decommissioned. The comparison between measured and calculated
radioactivity in the JPDR core components showed a relatively good
agreement (factor of 2), and it was cleared that water content and
weight ratio of steel bars to concrete materials significantly
influenced the neutron flux distribution in the biological shield
(factor of 2-10 error). The measured radioactivity inside of the
reactor pressure vessel wall and at the inner part of the biological
shield was compared in detail with the calculations to verify the
methodology applied to calculations of radioisotope production. Then
it was found that the radioactive inventory could be estimated
accurately with combination of calculations and measurement of
radioactivity in samples and dose rate distribution for planning of
dismantling activities.
Keywords : Reactor Decommissioning, JPDR, Radioactive Inventory,
Neutron Activation, Core Internal, Reactor Pressure Vessel, Biological
Shield Concrete, Neutron Transport Calculation, ORIGEN, Thermal Neutron
Flux, Measurement of Radioactivity, Dose Rate, Chemical Analysis,
Radioactive Waste,
This study was conducted under contract with Science and Technology Agency of Japan
from 1996 to 2000.+ Office of Operational Safety Administration
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JAERI-Tech 2001-058
Contents
1. Introduction 1
2. Technology for Estimation of Radioactive Inventory 2
2.1 Outline of Technology for Estimation of Radioactive Inventory 2
2.2 Outline of Reference Reactor 2
3. Calculation Method 2
3.1 Calculation Flow 2
3.2 Neutron Flux Calculation 2
3.3 Radioactivity Calculation 4
4. Measurement 5
4.1 Measurement Method 5
4.2 Dose Rate Measurement 5
4.3 Sampling before Reactor Dismantling 6
4.4 Sampling during and after Reactor Dismantling 7
4.5 Method of Radio-nuclide Analysis 7
5. Results 8
5.1 Calculation 8
5.2 Measurement 9
6. Discussion 11
6.1 Comparison between Calculated Value and Measured Value 11
6.2 Discussion on Discrepancies of Calculated Results 12
6.3 Discussion on Procedure for Radioactive Inventory Evaluation 14
7. Concluding Remarks 15
Acknowledgement 16
References 17
Appendix I Outline of Major Components 41
Appendix II Manufacturing Dose Rate Measuring Devices and Sampling Devices for
Reactor Components 50
AppendixM Measurement Results of Dose Rate and Radioactivity 54
AppendixIV Chemical Analysis 66
Appendix V Parametric Calculation for Radioactive Inventory Evaluation 68
AppendixVI Application of Radioactive Inventory Data for a Reactor Dismantling Project 80
JAERI-Tech 2001-058
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JAERI-Tech 2001-058
Table and Figures Captions
Table 1 Major Specification of Reactor
Table 2 Energy Group Structures of 48 Groups Library
Table 3 Atomic Number Density for the Materials in Reactor
Table 4 Nuclide Contents of Structural Materials and Impurity Elements (w%)
Table 5 Operational History
Table 6 Radioactive Inventory in Neutron-Activated Components
Table 7 Measured Radioactivity in Major Components (Direct Measurement)
Table 8 Measured Radioactivity in Major Components (Chemical Analysis)
Fig.l Schematic View of Reactor Enclosure Building
Fig.2 Reactor Core and Fuel Assembly
Fig.3 Reactor Pressure Vessel and Core Internals
Fig.4 Flow Diagram of Radioactive Inventory Calculation Code System
Fig.5 One-dimensional Model for ANISN Calculations (Vertical and Horizontal Plane)
Fig.6 Two-dimensional Model of Middle Part of Reactor for DOT3.5 Calculations
Fig.7 Simplified Operational History
Fig.8 Schematic View of Reactor and Sampling Positions
Fig.9 Thermal Neutron Flux Contour
Fig. 10 Radial Flux Distribution at Core Midplane
Fig.ll Discrepancies between Calculation and Measurement of Radioactivity in Reactor Components
Fig. 12 Vertical Radioactivity Distribution at Inner Surface of Core Shroud and Reactor Pressure Vessel
Fig. 13 Radioactivity Distribution in Reactor Pressure Vessel Wall
Fig. 14 Discrepancies between Calculation and Measurement of Radioactivity in Biological Shield
Fig. 15 Horizontal 60Co Activity Distribution in Biological Shield (Core A —C)
Fig. 16 Horizontal 60Co Activity Distribution in Biological Shield (Core D —F)
Fig. 17 Horizontal Radioactivity Distribution of Gamma-emitter Nuclides in Biological Shield (Core D)
Fig.18 Radioactivity Distribution in Biological Shield Liner
Fig. 19 Vertical Radioactivity Distribution at Inner Surface of Biological Shield
Fig.20 Detail Flux Calculation around Control Rod
Fig.21 Relation between Water Content and Thermal Neutron Flux Distribution in Concrete Biological
Shield
Fig.22 Neutron Flux Distributions Calculated Changing Weight Ratio of Steel Bars in the Inner Layer of
Biological Shield
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(2) rty?X>\*mffl:m¥P!m^m%imt^&-JFDR<Dmfc£&ffiM%-, JAERI-Tech
97-001(1997)
(3) Engle Jr.,W. W. : A User's Manual for ANISN, A One-Dimensional Discrete Ordinates Transport Code
With Anisotropic Scattering, K-1693(1967)
(4) Mynatt, F. R. et al. : The DOT-m Two-Dimensional Discrete Ordinates Transport Code, ORNL-TM-
4280(1973)
(5) Bell, M. J.: ORIGEN - The ORNL Isotope Generation and Depletion Code, ORNL4628(1973)
(6) PSR-63/AMPX-II Document Package : AMPX-II : Modular Code System for Generating Coupled
Multigroup Neutron-Gamma-Ray Cross-Section Libraries from Data in ENDF Format, ORNL
(7) DLC-41/VITAMIN-C DATA PACKAGE : VTTAMIN-C : 171 Neutron, 36 Gamma-Ray Group Cross
Sections in AMPX and CCCC Interface Formats for Fusion and LMFBR Neutronics, ORNL
(8) Naito, Y. et al. : MGCL-PROCESSOR : A Computer Code System for Processing Multigroup Constants
Library MGCL, JAERI-M 9396(1981)
(9) /hlililn, ffi : ffiBfflft(Dffi8fc, JAERI-M 6928(1977)
(10) Delp, D. L. et al.: FLARE - A Three-Dimensional Boiling Water Reactor Simulator, GEAP-4598(1964)
(11) Watt, B. E.: Phys. Rev., 87,1037(1952)
(12) J. C. Evans et al.: Long-Lived Activation Products in Reactor Materials, NUREG/CR-3474(1984)
(13) GE: APED3998 JPDR Final Design Report(1962)
(14) JPDR JEE^&ggffrnr tW"!^ ON«fiE±, ffi) : W]tjMMfc'}Pl±.tl^%s(DW, 2
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JAERI-Tech 2001-058
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- 7 4 -
JAERI-Tech 2001-058
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- 7 5 -
JAERI-Tech 2001-058
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0.9894.124E+102.780E+105.392E+09
1.0113.686E+102.702E+106.722E+09
1.0183.338E+102.648E+108.370E+09
1.0229.338E+091.588E+102.646E+10
1.0301.777E+042.422E+041.272E+05
0.7541.080E-011.497E-017.854E-01
0.756
- 7 6 -
JAERI-Tech 2001-058
!V-2(3-2)
(cm)
0.0
63.2
70.0
79.7
89.0
104.1
110.0
111.0
116.5
135.6
145.0
281.0
411.0
m H *
m,
*
3 ^ ^7 U — b1
13 ^/ ' J'—* S
60 03.763E+133.388E+131.681E+13
1.0062.338E+131.801E+131.143E+13
1.0035.286E+126.022E+123.069E+13
0.9671.301E+121.112E+122.786E+12
0.9172.695E+112.266E+111.509E+12
0.8877.120E+104.576E+104.339E+10
0.9224.707E+102.935E+104.338E+09
0.9944.123E+102.779E+105.382E+09
1.0093.686E+102.700E+106.694E+09
1.0133.338E+102.646E+108.324E+09
1.0169.339E+091.588E+102.638E+10
1.0271.777E+042.422E+041.452E+05
0.8611.080E-011.497E-018.958E-01
0.862
75 03.763E+133.388E+131.674E+13
1.0022.338E+131.801E+131.143E+13
1.0035.286E+126.022E+123.143E+13
0.9901.301E+121.112E+122.934E+12
0.9662.695E+112.266E+111.616E+12
0.9497.120E+104.577E+104.533E+10
0.9634.708E+102.935E+104.349E+09
0.9974.124E+102.779E+105.359E+O9
1.0053.686E+102.701E+106.650E+09
1.0073.339E+102.647E+108.256E+09
1.0089.340E+091.588E+102.605E+10
1.0141.777E+042.422E+041.573E+05
0.9321.080E-011.497E-019.701E-01
0.934
90 03.763E+13
' 3.388E+131.671E+13
1.0002.338E+131.801E+131.141E+13
1.0015.286E+126.022E+123.169E+13
0.9981.301E+121.112E+123.017E+12
0.9932.695E+112.265E+111.682E+12
0.9887.121E+104.580E+104.669E+10
0.9924.710E+102.939E+104.369E+09
1.0024.126E+102.783E+105.342E+09
1.0013.688E+102.704E+106.619E+09
1.0023.340E+102.650E+108.208E+09
1.0029.343E+091.590E+102.577E+10
1.0031.778E+042.423E+041.659E+05
0.9831.080E-011.497E-011.022E+00
0.984
96 03.763E+133.388E+131.671E+13
1.0002.338E+131.801E+131.140E+13
1.0005.286E+126.022E+123.174E+13
1.0001.301E+121.113E+123.037E+12
1.0002.695E+112.265E+111.702E+12
1.0007.121E+104.578E+104.708E+10
1.0004.709E+102.936E+104.362E+09
1.0004.125E+102.781E+105.334E+09
1.0003.687E+102.702E+106.606E+09
1.0003.340E+102.648E+108.189E+09
1.0009.342E+091.589E+102.569E+10
1.0001.778E+042.422E+041.687E+05
1.0001.080E-011.497E-011.039E+00
1.000
- 7 7 -
JAERI-Tech 2001-058
tv-3 ANISN
48 S¥
bfc48 S¥
DB-Hif
ilb
89m
CPU(*)
2.92
7.35
11.77
12.83
2.72
9.00
11.22
12.27
0.83
6.35
16.48
31.20
45.20
58.27
70.64
82.32
87.35-
11.87
OUTER
5
15
30
35
5
15
30
35
1
5
15
30
45
60
75
90
96
36
INNER(0)
2722
6915
10251
10802
2721
6943
10270
10822
877
4395
10929
19428
26893
33138
38390
42783
44686
10773
NEUTJBAL
1.0000105
1.0000105
1.0000095
1.0000124
1.0000143
1.0000134
1.0000124
1.0000143
1.0000191
1.0000095
1.0000076
1.0000086
1.0000076
1.0000067
1.0000076
1.0000076
1.0000086
1.0000095
UPSCATTERRATIO
1.0419760
1.0051031
1.0003405
1.0001488
1.0427408
1.0051546
1.0003414
1.0001478
0.0
1.0195398
1.0037527
1.0014753
1.0006189
1.0002699
1.0001183
1.0000601
1.0000362
1.0001421
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.0158014
1.0032320
1.0002422
1.0001030
1.0158663
1.0032368
1.0002365
1.0001020
0.0
1.0505123
1.0099592
1.0054998
1.0026741
1.0012674
1.0005798
1.0002489
1.0001841
1.0000696
"" (**)
0.468
0.859
0.993
1.000
0.468
0.860
0.993
1.000
-
0.310
0.491
0.698
0.834
0.917
0.966
0.993
1.000
-
ANISNEPS = 1.0X10"" : epsilon - accuracy desiredRYF =0.5 : A 2 relaxation factor, normally 0.5XLAL = 1.0 X 10~4: point flux convergence criterion if entered
greater than zero
1.00
- 7 8 -
JAERI-Tech 2001-058
1.2
1.0
0-8
0.6
•fr8 0.4
0.2
0.020 40 60 80 100
JV-4
1.0E+09
1.0E+08
o<Dtl)
CM
E 1.0E+07
| j 1.OE+06
1.0E+05
1.0E+04
**" \v • .
\ : : : : : : :
\ . : : : : . :: y'.'.'.'.
o
>
x
1
- • DOT3.5 I- M O R S E [I
^ : ^ v _ : : : : : . . - : : : : : :
• ' • • ' :
1.0E+07
1 .OE+06
1.0E+03
1.OE+0250 100 150 200 250
- 7 9 -
JAERI-Tech 2001-058
CR)
40cm
lm
40cm
FCD-37 m
PL, PC ^ r ; CR
A,
JPDR m
, 6 mm (A, B, C, PL, PQ
-5
(LXWXH)Gum) Gum) fton)
(m3)(Ba)
(MSv/h)
lm1,370 X,370
X 1,382330 15.0 0.36 93T 160 70
B1,370X1,370
X 1,382 235 13.4 0.73 5.6T 140 70
1,370X1,370X 1,250
70 4.7 1.33 22G 100 60
PL 1,050X1,050X 2,728
375 17.7 0.18 28T 260 70
PC1,060X1,060
X 2,633325 17.0 0.34 4.8T 300 70
CR1,060X1,060
X 2,593305 16.4 0.40 umm 2.4T 500 80
- 8 0 -
JAERI-Tech 2001-058
t l O
0 0 . 5 1 . 0 1 - 5 2 - 0 2 . 5 3 . 0 3 - S 4 - 0
a 4.0 +
1.0
RRDtf iL DISrBNCE (CH)
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- 8 1 -
(SI) t
ftK
Mmi®
4
t i
3
eef*
s i *
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SffiFmu*.ftKftft
6*
+
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7
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D 9' 7
y /-;Jl/ h"
y x
^ Tx x 7 'y 7
71/
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71/
7
y
y
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mkgsAK
molcd
radsr
Sljgfflli
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iit
a
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SB
&"&
ti , tt
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a • . -i. HE. i
m s« ffi
y 9" 9 9
y 9' 9 9iv y o 7.
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5
tsy x
y 7fi S
mmm.
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i / 3. —
9 -/? — D
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7 T 7
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9 x —x X-v y 'J-te ;i/ -y ^ ?^ - ^
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7y
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by
b
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s->m-kg/s2
N/m2
N-mJ/sA-sW/AC/VV/AA/VV-sWb/m2
Wb/A
cd-srlm/m2
s -J/kgJ/kg
y
b
1
1
B#, a
y
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12
min,
1, Lt
eVu
eV=1.602l8xl0-
u= 1.66054x10""
h, d
9 J
kg
m4
* y?',<
/<
if+ j .
i/ y
7
u
ft7. b o - A— y- 71/
7U
'J -
b ¥ yK
A
IS ^•
Ab
barGalCiR
radrenv
1 A=0.1 nm=10-'°m
1 b=100fm2=10-28m2
lbar=0.1MPa=105Pa
1 Gal=lcm/s2 = 10-2rn/s2
lCi=3.7xlO"Bq
1 R=2.58xlO-4C/kg
1 rad = lcGy=10"2Gy
1 rem=lcSv=10"2Sv
10"10"10'2
109
106
103
102
10'
10"'
lO"2
io-3
10"'
io-9
10""10""I O - "
mX
" !
X
* *
+
X
X
•fe
X
f
7
T
9 -r
7
* *
ifa
9 bt
•y
y -31
'j
-f 9 Dy13
x A h
H
IS -^
EPTGMkhda
dcmun
Pfa
i. m 1 - 5 1 4
Sg.W&Wi 1985^flJ?flCj;4o izfiL, 1 eV
fc i O* 1 u fflfl(4 CODATA © 1986 3E}fSg
2.
3. bar (4,
. barnfciIf
N( = 10sdyn)
1
9.80665
4.44822
kgf
0.101972
1
0.453592
lbf
0.224809
2.20462
1
tt / t 1 Pa-s(N-s/m2)=10P(#TX)(g/(cm-s))
1 mVs=10'StCx h -
E MPa(=10bar)
1
0.0980665
0.101325
1.33322 x 10"
6.89476 x 10"3
kgf/cm !
10.1972
1
1.03323
1.35951 x 10"3
7.03070 x 10"2
atm
9.86923
0.967841
1
1.31579 xlO"3
6.80460 x 10-2
mmHg(Torr)
7.50062 x 103
735.559
760
1
51.7149
Ibf/in2(psi)
145.038
14.2233
14.6959
1.93368 x 10"2
1
X
IV
¥1
tt
«
J( = 10'erg)
1
9.80665
3.6 xlO6
4.18605
1055.06
1.35582
1.60218 x 10""
kgf-m
0.101972
1
3.67098 x 10 s
0.426858
107.586
0.138255
1.63377 xlO"20
kW- h
2.77778x10"
2.72407X10'6
1
1.16279 x 10'6
2.93072 x 10"
3.76616x10"
4.45050 xlO"26
cal(!t«ft)0.238889
2.34270
8.59999x10'
1
252.042
0.323890
3.82743 xlO"2°
Btu
9.47813x10-'
9.29487 x 10"3
3412.13
3.96759 x 10~3
1
1.28506 xlO'3
1.51857x10'"
ft • lbf
0.737562
7.23301
2.65522 x 10s
3.08747
778.172
1
1.18171 x 10"19
eV
6.24150x10"
6.12082x10"
2.24694x10"
2.61272x10"
6.58515 xlO2 '
8.46233x10"
1
1 cal = 4.18605 J(ttMffi)
= 4.184J (SBKt^)
= 4.1855 J (15 °C)
75 kgf-m/s
735.499 W
Bq
3.7 x 10"
Ci
2.70270 x 10""
1
Gy
1
0.01
rad
100
1
C/kg
2.58 x 10"
3876
1
Sv
1
0.01
100
1
(86ipi2J3 26
imit
kif*
1