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Cs activity in spent nuclear fuel with calculated detector response functionSato, Shunsuke*; Nauchi, Yasushi*; Hayakawa, Takehito*; Kimura, Yasuhiko; Kashima, Takao*; Futakami, Kazuhiro*; Suyama, Kenya
Journal of Nuclear Science and Technology, 60(6), p.615 - 623, 2022/06
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)A new non-destructive method for evaluating Cs activity in spent nuclear fuels was proposed and experimentally demonstrated for physical measurements in burnup credit implementation. Cs activities were quantified using gamma ray measurements and numerical detector response simulations without reference fuels, in which Cs activities are well known. Fuel samples were obtained from a lead use assembly (LUA) irradiated in a commercial pressurized water reactor (PWR) up to 53 GWd/t. Gamma rays emitted from the samples were measured using a bismuth germinate (BGO) scintillation detector through a collimator attached to a hot cell. The detection efficiency of gamma rays with the detector was calculated using the PHITS particle transport calculation code considering the measurement geometry. The relative activities of 
Cs, Cs, and 
Eu in the sample were measured with a high-purity germanium (HPGe) detector for more accurate simulations of the detector response for the samples. The absolute efficiency of the detector was calibrated by measuring a standard gamma ray source in another geometry. Cs activity in the fuel samples was quantified using the measured count rate and detection efficiency. The quantified Cs activities agreed well with those estimated using the MVP-BURN depletion calculation code.
Kikuchi, Takeo; Tada, Kenichi; Sakino, Takao; Suyama, Kenya
JAEA-Research 2017-021, 56 Pages, 2018/03
JAEA-Research-2017-021.pdf:2.15MBJAEA-Research-2017-021(errata).pdf:0.13MB
The criticality management of the fuel debris is one of the most important research issues in Japan. The current criticality management adopts the fresh fuel assumption. The adoption of the fresh fuel assumption for the criticality control of the fuel debris is difficult because the k
of the fuel debris could exceed 1.0 in most of cases which the fuel debris contains water and does not contain neutron absorbers such as gadolinium. Therefore, the adoption of the burnup credit is considered. The prediction accuracy of the isotopic composition of used nuclear fuel must be required to adopt the burnup credit for the treatment of the fuel debris. JAEA developed a burnup calculation code SWAT4.0 to obtain reference calculation results of the isotopic composition of the used nuclear fuel. This code is used to evaluate the composition of fuel debris. In order to investigate the prediction accuracy of SWAT4.0, we analyzed the PIE of BWR obtained from 2F2DN23.
Nomura, Yasushi*; Okuno, Hiroshi; Miyoshi, Yoshinori
JAERI-Tech 2004-030, 64 Pages, 2004/03
JAERI-Tech-2004-030.pdf:4.59MB
no abstracts in English
Nomura, Yasushi; Mochizuki, Hiroki*
JAERI-Tech 2002-068, 131 Pages, 2002/11
JAERI-Tech-2002-068.pdf:5.59MB
no abstracts in English
Nuclear Code Evaluation Special Committee of Nuclear Code Research Committee
JAERI-Review 2002-003, 97 Pages, 2002/03
JAERI-Review-2002-003.pdf:8.64MB
no abstracts in English
Nomura, Yasushi; Murazaki, Minoru*; Okuno, Hiroshi
JAERI-Data/Code 2001-029, 120 Pages, 2001/11
JAERI-Data-Code-2001-029.pdf:6.16MB
no abstracts in English
Nakahara, Yoshinori; Suyama, Kenya; Suzaki, Takenori
JAERI-Tech 2000-071, 381 Pages, 2000/10
JAERI-Tech-2000-071.pdf:17.6MB
no abstracts in English
Suzaki, Takenori; Suyama, Kenya; Kaneko, Toshiyuki*
Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), 4, p.1386 - 1393, 1999/00
no abstracts in English
17 PWR fuel assemblySuyama, Kenya; Nakahara, Yoshinori; Kaneko, Toshiyuki*;
Proc. of PATRAM'98, 1, p.239 - 244, 1998/00
no abstracts in English
Suyama, Kenya; *; *
JAERI-Data/Code 97-047, 128 Pages, 1997/11
JAERI-Data-Code-97-047.pdf:3.06MB
no abstracts in English
Ru/
Ce and burnup analysesSato, Shunsuke*; Nauchi, Yasushi*; Hayakawa, Takehito*; Kimura, Yasuhiko; Suyama, Kenya
no journal, ,
We evaluated the activity ratio ofRu to Ce by measurement of polyethylene-transmitted 
radiation from used nuclear fuel cooled more than 10 years. We confirmed that the ratio could be used for the burnup confirmation because we could obtain good agreement between calculation and experiment.
