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Suyama, Kenya; Ueki, Taro; Gunji, Satoshi; Watanabe, Tomoaki; Araki, Shohei; Fukuda, Kodai; Yamane, Yuichi; Izawa, Kazuhiko; Nagaya, Yasunobu; Kikuchi, Takeo; et al.
Proceedings of 12th International Conference on Nuclear Criticality Safety (ICNC2023) (Internet), 6 Pages, 2023/10
To remove and store safely the fuel debris generated by the severe accident of the Fukushima Daiichi Nuclear Power Station in 2011 is one of the most important and challenging topics for decommissioning of the damaged reactors in Fukushima. To validate the adopted method for the evaluation of criticality safety control of the fuel debris through comparison with the experimental data obtained by the criticality experiments, the Nuclear Regulation Authority (NRA) of Japan funds a research and development project which was entrusted to the Nuclear Safety Research Center (NSRC) of Japan Atomic Energy Agency (JAEA) from 2014. In this project, JAEA has been conducting such activities as i) comprehensive computation of the criticality characteristics of the fuel debris and making database (criticality map of the fuel debris), ii) development of new continuous energy Monte Carlo code, iii) evaluation of criticality accident and iv) modification of the critical assembly STACY for the experiments for validation of criticality safety control methodology. After the last ICNC2019, the project has the substantial progress in the modification of STACY which will start officially operation from May 2024 and the development of the Monte Carlo Code "Solomon" suitable for the criticality calculation for materials having spatially random distribution complies with the power spectrum. We present the whole picture of this research and development project and status of each technical topics in the session.
spectrum model of randomizationSimanullang, I.; Yamane, Yuichi; Kikuchi, Takeo; Tonoike, Kotaro
Annals of Nuclear Energy, 147, p.107675_1 - 107675_6, 2020/11
Times Cited Count：2 Percentile：24.28(Nuclear Science & Technology)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.
Tada, Kenichi; Kikuchi, Takeo*; Sakino, Takao; Suyama, Kenya
Journal of Nuclear Science and Technology, 55(2), p.138 - 150, 2018/02
Times Cited Count：3 Percentile：30.05(Nuclear Science & Technology)The criticality safety of the fuel debris in Fukushima Daiichi Nuclear Power Plant is one of the most important issues and the adoption of the burnup credit is desired for the criticality analysis. The assay data of used nuclear fuel irradiated in 2F2 is evaluated to validate SWAT4.0 for BWR fuel burnup problem. The calculation results revealed that number density of many heavy nuclides and FPs showed good agreement with the experimental data except for 
U, 
Np, 
Pu and Sm isotopes. The cause of the difference is assumption of the initial number density and void ratio and overestimation of the capture cross section of Np. The C/E-1 values do not depend on the types of fuel rods (UO
or UO-GdO
) and it is similar to that for the PWR fuel. These results indicate that SWAT4.0 appropriately analyzes the isotopic composition of the BWR fuel and it has sufficient accuracy to be adopted in the burnup credit evaluation of the fuel debris.
Wakai, Eiichi; Kim, B. J.; Nozawa, Takashi; Kikuchi, Takayuki; Hirano, Michiko*; Kimura, Akihiko*; Kasada, Ryuta*; Yokomine, Takehiko*; Yoshida, Takahide*; Nogami, Shuhei*; et al.
Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 6 Pages, 2013/03
Takamura, Shuichi*; Kado, Shinichiro*; Fujii, Takashi*; Fujiyama, Hiroshi*; Takabe, Hideaki*; Adachi, Kazuo*; Morimiya, Osamu*; Fujimori, Naoji*; Watanabe, Takayuki*; Hayashi, Yasuaki*; et al.
Kara Zukai, Purazuma Enerugi No Subete, P. 164, 2007/03
no abstracts in English
Tsuzuki, Kazuhiro; Kimura, Haruyuki; Kawashima, Hisato; Sato, Masayasu; Kamiya, Kensaku; Shinohara, Koji; Ogawa, Hiroaki; Hoshino, Katsumichi; Bakhtiari, M.; Kasai, Satoshi; et al.
Nuclear Fusion, 43(10), p.1288 - 1293, 2003/10
Times Cited Count：39 Percentile：74.23(Physics, Fluids & Plasmas)no abstracts in English
Wakai, Eiichi; Kikuchi, Kenji; Yamamoto, Shunya; Aruga, Takeo; Ando, Masami; Tanigawa, Hiroyasu; Taguchi, Tomitsugu; Sawai, Tomotsugu; Oka, Keiichiro*; Onuki, Somei*
Journal of Nuclear Materials, 318, p.267 - 273, 2003/05
Times Cited Count：70 Percentile：96.81(Materials Science, Multidisciplinary)no abstracts in English
Wakai, Eiichi; Sawai, Tomotsugu; Furuya, Kazuyuki; Naito, Akira; Aruga, Takeo; Kikuchi, Kenji; Yamashita, Shinichiro*; Onuki, Somei*; Yamamoto, Shunya; Naramoto, Hiroshi; et al.
Journal of Nuclear Materials, 307-311(Part.1), p.278 - 282, 2002/12
Times Cited Count：51 Percentile：93.7(Materials Science, Multidisciplinary)no abstracts in English
Kikuchi, Shin; Kitazawa, Takeo; ; Matsumoto, Shinichiro
JNC TN9410 2001-003, 84 Pages, 2000/07
JNC-TN9410-2001-003.pdf:2.12MB
Eddy current techniques have been tested for future Post irradiated Experiment ;PIE applications outside hot cell(the following, cell outside). As the result, applicability to the defects inspection such as the cladding tube material was able to be confirmed, and an outlook to the application to the irradiation material was obtained. The last time, report described results of the external surface defects, inside defects, and open holes outside hot cell except for Fuel-Cladding Chemical Interaction (FCCI) measurement testing This paper mainly describes the results of the trial FCCI measurement testing outside hot cell. Other tests include the results of external surface defects, inside defects, and open holes in the proofreading tests. The proofreading tests used a standard defect pin inside hot cell. In the trial FCCI measurement testing outside hot cell, the correlation between reduction in thickness and eddy current signal value was comfirmed, and the prospect of FCCI measurement by the eddy current testing was examined. As the result, the optimum conditions for measuring the FCCI quantity are respectively (1)carrier speed of the pin :20mm/sec, (2) test frequency : 32kHz, (3)phase : ODEG, (4) gain :-10dB, (5)filter : 0. The correlation between trial FCCI quantity and eddy current signal value was found on the basis of the test result, and the prospect which could detect FCCI was obtained when there is reduction in thickness of over 50 
m for the cladding tube with wall thickness quantity of the 300 m order. And, the proofreading test inside hot cell on eddy current measurements were confirmed to be equivalent to the performance test outside hot cell.
Shirai, Hiroshi; Takizuka, Tomonori; Kikuchi, Mitsuru; Mori, Masahiro; Nishitani, Takeo; Ishida, Shinichi; Kamada, Yutaka; Sato, Masayasu; Isei, Nobuaki; Koide, Yoshihiko; et al.
IAEA-CN-60/A2-17, 0, p.355 - 364, 1995/00
no abstracts in English
Tobita, Kenji; Tani, Keiji; Kusama, Yoshinori; Nishitani, Takeo; Ikeda, Yoshitaka; Neyatani, Yuzuru; S.V.Konovalov*; Kikuchi, Mitsuru; Koide, Yoshihiko; Hamamatsu, Kiyotaka; et al.
Nuclear Fusion, 35(12), p.1585 - 1591, 1995/00
Times Cited Count：68 Percentile：88.29(Physics, Fluids & Plasmas)no abstracts in English
dischargesKoide, Yoshihiko; Kikuchi, Mitsuru; Mori, Masahiro; Tsuji, Shunji; Ishida, Shinichi; Asakura, Nobuyuki; Kamada, Yutaka; Nishitani, Takeo; Kawano, Yasunori; Hatae, Takaki; et al.
Physical Review Letters, 72(23), p.3662 - 3665, 1994/06
Times Cited Count：265 Percentile：98.52(Physics, Multidisciplinary)no abstracts in English
Nishitani, Takeo; Ishida, Shinichi; Kikuchi, Mitsuru; Azumi, Masafumi; Yamagiwa, Mitsuru; Fujita, Takaaki; Kamada, Yutaka; Kawano, Yasunori; Koide, Yoshihiko; Hatae, Takaki; et al.
Nuclear Fusion, 34(8), p.1069 - 1079, 1994/00
Times Cited Count：29 Percentile：69.04(Physics, Fluids & Plasmas)no abstracts in English
Ishida, Shinichi; Matsuoka, Mamoru; Kikuchi, Mitsuru; Tsuji, Shunji; Nishitani, Takeo; Koide, Yoshihiko; Ozeki, Takahisa; Fujita, Takaaki; Nakamura, Hiroo; Hosogane, Nobuyuki; et al.
Plasma Physics and Controlled Nuclear Fusion Research 1992, Vol.1, p.219 - 233, 1993/00
no abstracts in English
Nagashima, Keisuke; Fukuda, Takeshi; Kikuchi, Mitsuru; Hirayama, Toshio; Nishitani, Takeo; Takeuchi, Hiroshi
Nuclear Fusion, 30(11), p.2367 - 2375, 1990/11
Times Cited Count：7 Percentile：32.57(Physics, Fluids & Plasmas)no abstracts in English
Kikuchi, Mitsuru; Ando, Toshiro; Araki, Masanori; ; Horiike, Hiroshi; Ikeda, Yoshitaka; ; Koizumi, Koichi; Matsukawa, Makoto; ; et al.
Fusion Technology 1988, p.287 - 292, 1989/00
no abstracts in English
Matsukawa, Makoto; Ando, Toshiro; Araki, Masanori; ; Horiike, Hiroshi; Ikeda, Yoshitaka; Kikuchi, Mitsuru; ; Koizumi, Koichi; ; et al.
Fusion Technology 1988, p.293 - 297, 1989/00
no abstracts in English
JRR-2 Critical Experiments Group; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Morozumi, Minoru; Kambayashi, Yuichiro; Shitomi, Hajimu; Kokanezawa, Takashi; et al.
JAERI 1025, 62 Pages, 1962/03
no abstracts in English
Wakai, Eiichi; Kikuchi, Takayuki; Hirano, Michiko; Ida, Mizuho; Niitsuma, Shigeto; Kimura, Haruyuki; Nishitani, Takeo; Yamamoto, Michiyoshi; Matsumoto, Hiroshi; Sugimoto, Masayoshi; et al.
no journal, ,
no abstracts in English
