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JAEA
-EvaluationJAEA-Evaluation
2011-002
外部専門家による平成22年度炉心確認試験に関する評価（もんじゅ研究利用専門委員会）
External Evaluation on Monju Core Confirmation Test in FY 2010
(the Technical Committee on Monju Research Utilization)
日本原子力研究開発機構
June 2011
Japan Atomic Energy Agency
FBRプラント工学研究センター 敦賀本部高速増殖炉研究開発センター
FBR Plant Engineering Center
Fast Breeder Reactor Research and Development Center,
Tsuruga Head Office
1.5% Am-241
Am-241 Pu-239
JENDL4.0
JAEA-Evaluation 2011-002
i
External Evaluation on Monju Core Confirmation Test in FY 2010
(the Technical Committee on Monju Research Utilization)
FBR Plant Engineering Center and
(Received March 28, 2011)
This report describes the review made by the “Technical Committee on Monju
Research Utilization” on the results of Core Confirmation Test conducted from May to July in 2010. The committee consists of technical specialists in the relevant engineering domains from various Japanese industries and universities.
The Committee was convened twice in 2010, in August and December, where the each item of the Core Confirmation Test was explained by individual personnel in charge, and the outline and the detailed analysis were discussed, respectively. Evaluations were made by the Committee after the questions and answers.
Main points of the evaluations are listed below: - After the 14 year stand-by, the Core Confirmation Test has been successfully
completed within a brief duration of 3 months, with provision of precious technical data for future development and commercialization of FBRs
- Safety has been confirmed and valuable data for analysis code validation have been acquired on an FBR core containing 1.5%wt of Am-241.
- It is significant that the newly released nuclear data library, JENDL-4.0 has been validated based on studies of capture cross section of Am-241 and of fission cross section of Pu-239.
Finally, the chief examiner of the Committee stated his expectation for advancement of Japanese FBR technologies with the JAEA’s leadership based of achievements on Monju, to be reflected on subsequent FBR developments. Keywords: Fast Breeder Reactor, Monju, Core Confirmation Test, External Evaluation
JAEA-Evaluation 2011-002
Fast Breeder Reactor Research and Development Center, Tsuruga Head Office Japan Atomic Energy Agency, Tsuruga-shi, Fukui-ken
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Contents 1. Monju System Start-up Tests 2. The Technical Committee on Monju Research Utilization 3. The Report and Evaluation on the System Start-up Tests at the Committee Meetings in JFY2022
noitaulavE llarevO .4 Acknowledgement Appendix
Explanations and Question/Answers on the System Start-up Tests at the Committee Meetings
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JAEA-Evaluation 2011-002
List of Tables Table 1 List of Names of the Technical Committee on Monju Research Utilization Table 2 List of Proposed Test Items by the Committee
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1521263440485560
676770
74
7878
11
18182430354349576469
767679
83
8787
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40
45 45
40
79
75
100100
Am241 :1.5Wt%/HMAm241 :0.5Wt%/HM
1
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2
241Am wt241Am
3
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6
252Cf
4
R&
D
241Pu
5
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FBR
6
178
241Am wt%
7
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8
9
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10
•FBR
• FBR
•FBR
11
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2
78 6Am
RID
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(2)炉心特性関係
① 制御 確認
矢吹 健太郎
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(CCR) (FCR) (BCR)
B C
1000mm
1100mm
830mm CCR FCR
CCR1 793mmCCR2 CCR10 795FCR1 FCR3 795
930mm
775mm
830mm
(S0/Sn)
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C2,3,4 0.15%
C5,7,9 0.40%
C6,8,10 0.35%
F1,2,3 0.24%
B1,2,3 0.17%
B4,5,6 0.19%
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S
FCRFCR
CCR FCRFCR CCR FCR
2
1
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②炉
加藤 優子
1
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2
3
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4
i
t-ii
t-CfCf
iCf ens ensN(t)
a. b.
t-iii
iens(t)S
act-
Cf NeNN(t) Cf
5
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act-
Cf NeNN(t) Cf
6
t-iii
iens(t)S
7
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i
t-AcAc
t-CfCf
iCf ens ensN(t)
9-SRM
9-SRM
-9SRM
-9SRM
10×4.1:,10×4.5:
10×1.1:,10×7.4:
8
9
JAEA-Evaluation 2011-002
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effAc
effCf K-1
1×S×+K-11×S×=N
10-SRM
10-SRM
-10SRM
-10SRM
10×2.2:,10×5.8:
10×7.1:,10×3.7:
10
11
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高野 和也
R&D
14 [MW]
1
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WRM
WRMSRM
WRM
WRM
2
WRM
2%
SRM
WRM
PRM
235U HV
235U
40 [cps/nv]
0.3 [cps/nv]
100 [cps]1.2 10-8 [%]
100 [cps]
/105 [cps]
DC
105 [cps]1.2 10-3 [%]
109 [cps]
120%
3
JAEA-Evaluation 2011-002
-31-
1.E+02
1.E+03
1.E+04
1.E+05
1.E+06
0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 [V]
[cps
]
WRM ch1WRM ch2WRM ch3
1log(N|V=Vn N|V=3) 1.0 N
Vn 3 [V]
WRM ch1 WRM ch2 WRM ch3
Vn 3 [V] 0.57 0.36 0.53
[V]6 1.0 (1.6) 1.2 (1.9) 1.1 (1.7)
WRM
Vn
4
1.E+03
1.E+04
0 200 400 600 800 [V]
[cps
]
WRM ch1WRM ch2WRM ch3
WRM
100 [V]
0.1 [%/V]
WRM ch1 WRM ch2 WRM ch3
[V] 650 700 650
[%/V] 0.009 0.020 0.012
[V] 400 400 400
400 [V]
5
JAEA-Evaluation 2011-002
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2.6
6 2.56
239 1 105 [cps]
SRM WRM
239 [cps]
WRM ch1
WRM ch2
WRM ch3
SRM ch1
SRM ch2
log10(105/239)2.6
1.5 [cps]
1
[cps]
[cps]
[cps]
[cps]
[cps]
WRM [cps]SRM [cps]
SRM WRM
1
10
100
100 1000 10000SRM ch1 [cps]
WR
M [c
ps]
WRM ch1WRM ch2WRM ch3
SRM
WR
M
6
(1/2)
WRM
6 SRM6
SWP
P SRM WRM
P [MW]W WRM [cps]S SRM [cps]
WRM [MW/cps]WRM SRM [-]
22226006 HHHH
22
060622
H
HHH
H06 6 H22
7
JAEA-Evaluation 2011-002
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1
10
100
100 1000 10000SRM ch1 [cps]
WR
M [c
ps]
WRM ch1WRM ch2WRM ch3
1
10
100
100 1000 10000SRM ch2 [cps]
WR
M [c
ps]
WRM ch1WRM ch2WRM ch3
(2/2)
SRM ch1 WRM SRM ch2 WRM
6H06 12.39 10-6 [MW/cps]
SRM WRM
H22 10.23 10-6 11.23 10-6 [MW/cps]
– WRM
22
060622
H
HHH
14 [MW]1.06 106 [cps]
8
••• SRM WRM• WRM
••
( 14 [MW] ( ): 5.1 [MW])
9
40%
WRM PRM• DC WRM• PRM•
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毛利 哲也
④
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1
2
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T ed kT
TTT
kT
0
0lnTk
T
TTk ed
0
0ln
ed kXkY
1/T
ed kT
TTT
kT
0
0ln
X
Y
JAEA-Evaluation 2011-002
-40-
40
6
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-41-
FCA 10%
20% 25% FCA
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-42-
⑤
諸橋 裕子
1
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2
3
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(IHX)1
2
AC)
(EV)
(SH)
4
5
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6
7
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-46-
8
9
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200 300
100
2.5mm
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1
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AC
2
3ch
3
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4
1 5
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2 6
3
SH
EVIHXR/V TbAC
7
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2%
6
8
4
C2C3
C4
C5
C6
C7
C8
C9
C10
F1
F2
F3
B1
B2
B3 B4
B5
B6
C2C3
C4
C5
C6
C7
C8
C9
C10
F1
F2
F3
B1
B2
B3 B4
B5
B6
C2C3
C4
C5
C6
C7
C8
C9
C10
F1
F2
F3
B1
B2
B3 B4
B5
B6
C2C3
C4
C5
C6
C7
C8
C9
C10
F1
F2
F3
B1
B2
B3 B4
B5
B6
C2C3
C4
C5
C6
C7
C8
C9
C10
F1
F2
F3
B1
B2
B3 B4
B5
B6
C2C3
C4
C5
C6
C7
C8
C9
C10
F1
F2
F3
B1
B2
B3 B4
B5
B6
6
9
JAEA-Evaluation 2011-002
-53-
Core ConfirmationTest (CCT)
40%-power Confirmation Test (40%CT)
Power RisingTest (PRT)
RefuelingRefuelingReactor output (RO)Electricity output (EO)
EO:40%RO:45% 45
40%
7975%
100
RO: 0%
100RO
EO
T
T
10
11
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1
JAEA-Evaluation 2011-002
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Na 0.5
2 ACS
JAEA-Evaluation 2011-002
-56-
北野 彰洋
⑦未
CEA
1
JAEA-Evaluation 2011-002
-57-
-2 100
-2 -310 140
*1
Feynman-Rossi-
-203
*1
Feynman- GateTime
Rossi- 2 t dt
2
StCtNdk
kkd
1)(
1)(
6
1
d
)(tN)(tCk
)()()(
tCtNdt
tdCkk
k
k Ck( )
1Sk
d
0S
[cps
]
StCtNdk
kkd
1)(
1)(
6
1
6
1
)(k
kk tC
3
JAEA-Evaluation 2011-002
-58-
2 3sec
100nsec
4
SRM-ch2WRM-ch3
SRM-ch1WRM-ch1
WRM-ch2
SRM-ch2WRM-ch3
SRM-ch1WRM-ch1
WRM-ch2
(B-10 ) 2SRM (BF3 ) 2WRM ( ) 3
5
JAEA-Evaluation 2011-002
-59-
1
(-2 -20 -5 )
-100 ,-10 )
( )
10
6
C1 SRM Ch1
C6 SRM Ch1
2-2
7
JAEA-Evaluation 2011-002
-60-
SRM
8
SRM Ch1C1 Full-drop
SRM Ch1C1 Part-drop
1
SRM#1C1 -10[ ]
GateTime [sec]
Y[-]
GateTime [sec]
Y[-]
E-NIS#1C1 -10[ ]
GateTime [sec]
Y[-]
E-NIS#1C1 -2[ ]
SRM#1C1 -2[ ]
Feynman-Feynman-
-1
GateTime [sec]
-1
GateTime [sec]
9
JAEA-Evaluation 2011-002
-61-
E-NIS#1C1 -2[ ]
2
Rossi-Rossi-
E-NIS#1CR1 -10[ ]
SRM#1C1 -2[ ]
SRM#1C1 -10[ ]
10
-20
C1
Ch
11
JAEA-Evaluation 2011-002
-62-
SRM (
NIS) SRM
JAEA-Evaluation 2011-002
-63-
⑧崩
大川内 靖
1
JAEA-Evaluation 2011-002
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2
, , kJ/
•1
1
• R&D Na
Na 397 [ ] Na 17.36 [kg/s] Na 2384 [h]300 4%
6
3
JAEA-Evaluation 2011-002
-65-
MM: 1 MM: 1
1 49200
4
241Pu
5
• 241Pu• 40% 100%
• = + 241Pu
daykkkPu '/241 k/k day
JAEA-Evaluation 2011-002
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6
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⑨解
羽様 平
–
––
––––
1
JAEA-Evaluation 2011-002
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70g
(TriZ)
( )
JENDL-3.3
2
Pu241
(2
Pu241(Am241
3
JAEA-Evaluation 2011-002
-70-
---
---
::
4
JENDL-3.3(2002), JENDL-4.0(2010), ENDF/B-VII.0(2006)(1994/9) (2010/5)
0.990
0.992
0.994
0.996
0.998
1.000
1.002
1.004
1.006
JENDL-3.3 JENDL-4.0 ENDF/B-VII.0Nuclear data
keff
Previous (1994/9)
Present (2010/5)
(1 )
JENDL-3.3 keff
5
JAEA-Evaluation 2011-002
-71-
241Am 241Pu
( )
JENDL-3.3 -> JENDL-4.0 or ENDF/B-VII.0
241Am , 241Pu
Keff ( )
6
0.980
0.985
0.990
0.995
1.000
1.005
JENDL-3.3 JENDL-4.0 ENDF/B-VII.0Nuclear data
keff
-0.3
-0.2
-0.1
0.0
0.1
0.2A
ccur
acy
diff
. (%
k/kk
')
Previous (1994/9)Present (2010/5)Present-Previous
JENDL-3.3
7
JAEA-Evaluation 2011-002
-72-
–
:JENDL-3.3
-0.18% k/kk’
8
JENDL-3.3
JENDL-3.3 :241Am capture, 239Pu fission, 241Pu fission
JENDL-4.0 ENDF/B-VII.0 239Pu fissionJENDL-4.0 241Am capture 241Pu fission
9
JAEA-Evaluation 2011-002
-73-
------
241Am 241Pu241Am capture 241Pu fission
JENDL-3.3 JENDL-4.0
10
JAEA-Evaluation 2011-002
-74-
2 ±0.3% k/k
FaCT 2 ±0.6% k/k
Pu-241
Pu-241
Am-241
Am-241Am-241
Am-241Am-241
JENDL-4 Am-241 Pu-241
Am-241
JAEA-Evaluation 2011-002
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川村 義明 中川 浩樹 井田 拓美
(3) プラント特性関係（化学管理、放射線管理、機器設備） ①
122 17 16
2
3
4
JAEA-Evaluation 2011-002
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122 18 13
2
3
4
1.6ppm 1.5ppm 1.5ppm10ppm
2.3ppm3ppm
38ppm7500ppm
16ppm 5ppm 10ppm15000ppm
JAEA-Evaluation 2011-002
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130120
EVST
JAEA-Evaluation 2011-002
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川村 義明 中川 浩樹 井田 拓美
② 、
及び
122 17 16
2Na-22 Na-24
3
Na-22 Na-24
4
JAEA-Evaluation 2011-002
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122
2
3
4
40
4.4 10 Bq/ A1.0 10 Bq/
JAEA-Evaluation 2011-002
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122 11 21
2
3
4
A 0.00625 Sv/hB 0.01 Sv/h 0.0026 Sv/h
JAEA-Evaluation 2011-002
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久保 篤彦
1
JAEA-Evaluation 2011-002
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M-G
JAEA-Evaluation 2011-002
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M-G(Motor-Generator)
WWW
(
(
JAEA-Evaluation 2011-002
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JAEA-Evaluation 2011-002
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1
(4)
大草 享一
2
JAEA-Evaluation 2011-002
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3
4
t
t
JAEA-Evaluation 2011-002
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5
C22B( 558.8mm)
6
1.5( )
1.5
( )
JAEA-Evaluation 2011-002
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7t T
8
JAEA-Evaluation 2011-002
-90-
9
10
JAEA-Evaluation 2011-002
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11
W
W
W
WA
))()()((1)( 21 tWtWtWn
tW nA
12
20
JAEA-Evaluation 2011-002
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13
14
2
JAEA-Evaluation 2011-002
-93-
JSFR
JSFR
R&D
m sec
94
JAEA-Evaluation 2011-002
JST
95
JAEA-Evaluation 2011-002
200 200
40%
JSFR JSFR
FaCT
96
JAEA-Evaluation 2011-002
この印刷物は再生紙を使用しています
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