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O/HO vapor generator for contrast-variation neutron scatteringArima-Osonoi, Hiroshi*; Takata, Shinichi; Kasai, Satoshi*; Ouchi, Keiichi*; Morikawa, Toshiaki*; Miyata, Noboru*; Miyazaki, Tsukasa*; Aoki, Hiroyuki; Iwase, Hiroki*; Hiroi, Kosuke; et al.
Journal of Applied Crystallography, 56(6), p.1802 - 1812, 2023/12
Times Cited Count：0 Percentile：0.02(Chemistry, Multidisciplinary)Kawase, Keiichi; Kitano, Mitsuaki; Watanabe, Masanori; Yoshimura, Shuichi; Kikuchi, Shiro; Nishino, Katsumi*
JAEA-Review 2017-006, 173 Pages, 2017/03
JAEA-Review-2017-006.pdf:35.6MB
JAEA-Review-2017-006-appendix(CD-ROM).zip:0.52MB
Survey of a transition of the air and surface dose rate was conducted for the area where the Cabinet Office decontamination model demonstration project was implemented. The area includes 15 districts in 9 municipalities identified by the Ministry of the Environment. We investigated 11 times from October, 2012 to October, 2015. Measurement of the air dose rate in this study was carried out in two methods using the fixed-point measurement and gamma plotter H using a NaI scintillation survey meter etc. As fixed-point measurement, set measurement point in the first survey for (fixed point), it was subjected to measurement of the surface dose rate to continue (1cm height) and space dose rate (1m height). In addition surface specific dose rate distribution measurement using a gamma plotter H (5cm and 1m height) was also performed together. As a result of the fixed-point measurement and gamma plotter H surface measurements, space dose rate from the first survey to the 11th survey shows the downward trend. We consider that there is no movement of radioactive pollutants from outside decontamination model project area into decontamination model project area.
Ikusawa,Yoshihisa; Kikuchi, Keiichi; Ozawa, Takayuki; Nakazawa, Hiroaki; Isozaki,Takao*; Nagayama, Masahiro*
JNC TN8410 2005-012, 113 Pages, 2005/08
JNC-TN8410-2005-012.pdf:15.2MB
The E09 fuel assembly was irradiated in the FUGEN from February 1990 to January 1997. The fuel assembly was the highest burn-up assembly in FUGEN and the pellet peak burn-up reached about 48 GWd/t. The E09 fuel assembly was transported to Japan Atomic Energy Research Institute (JAERI) Tokai in 2001. Post Irradiation Examinations (PIE) were started in July 2001, and all PIE items were completed by March 2005. The irradiation behavior of E09 MOX fuel was evaluated from the result of PIE. The major results are as follows; The integrity of E09 fuel assembly and fuel rods was confirmed. The corrosion behavior of ATR MOX fuel cladding was similar to that of LWR-UO2 fuel cladding. The central void was observed in outer ring samples irradiated with the maximum linear power over 45kW/m. A porous fine structure, similar to the rim structure seen in LWR-UO
pellet, was observed in the circumferential region of MOX pellet and around the plutonium-rich spots. The MOX fuel properties irradiated up to ~48 GWd/t, which are pellet swelling, thermal conductivity, pellet melting temperature and diffusivity of fission gas, were similar to LWR-UO fuel properties. These results will be used for CANDU-OPTION program, which is one of Russian surplus weapon plutonium disposition programs with AECL in Canada, and available for LWR plutonium recycle program in Japan.
Ikusawa,Yoshihisa; Kikuchi, Keiichi; Ozawa, Takayuki; Nakazawa, Hiroaki; Abe, Tomoyuki; Isozaki,Takao*; Nagayama, Masahiro*
JNC TN8410 2004-008, 106 Pages, 2004/10
JNC-TN8410-2004-008.pdf:25.96MB
The "E09" was irradiated in the FUGEN from February 1990 to January 1997, and its average burn-up reached 37.7GWd/t at the end of irradiation. In order to be irradiated up to high burn-up, this fuel assembly had the design improved by applying the fissile content with axial distribution, four UO- GdO
fuel rods located with MOX fuel rods and so on. The E09 fuel assembly had been cooled in the FUGEN spent fuel pool for four years after irradiation.After that, it was transported to Japan Atomic Energy Research Institute (JAERI) Tokai in 2001.Post Irradiation Examinations (PIE) were started in July 2001 at Reactor Fuel Examination Facility in JAERI, and a part of destructive examinations(Puncture examination, Ceramography, Metallography and alpha-autoradiography) were completed in March 2003. The destructive examinations will be completed by December 2004.In this report, the data obtained from destructive examinations completed in March 2003 were summarized, and the evaluation results of irradiation performance of MOX fuel and cladding were discussed. Consequently, the MOX fuel rod integrity during irradiation was confirmed from the result of the destructive PIE. These results will be used for CANDU-OPTION program, which is one of Russian surplus weapon plutonium disposition programs with AECL in Canada, and available for LWR plutonium recycle program in Japan.
Ikusawa,Yoshihisa; Kikuchi, Keiichi; Nakazawa, Hiroaki; Abe, Tomoyuki; Isozaki,Takao*; Nagayama, Masahiro*
JNC TN8410 2003-015, 251 Pages, 2004/01
JNC-TN8410-2003-015.pdf:16.07MB
The FUGEN High Burn-up MOX Fuel Assembly E09 was developed for high burn-up fuel of DATR. The E09 MOX fuel assembly was irradiated at the FUGEN from February 1990 to January 1997, and its average burn-up reached 37.7GWd/t. In order to be irradiated up to high burn-up, they had the design improved by applying the fissile content with axial distribution, four UO2-Gd2O3 fuel rods and so on. The E09 fuel assembly had been cooled in the FUGEN spent fuel pool for four years after irradiation. After that, it was transported to Japan Atomic Energy Research Institute (JAERI) Tokai Research Establishment in 2001. Post Irradiation Examinations (PIE) were started in July 2001 at Reactor Fuel Examination Facility in JAERI, and a part of destructive examinations(Puncture examination ,Metallography and Alpha Autoradiography) were completed in March 2003. In this report, the data from destructive examinations will be summarized, and evaluation results of irradiation performance will be discussed. The integrity of fuel assembly during irradiation was confirmed in the destructive PIE.
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
Shibutani, Hideo*; Higashijima, Takahiro*; Ezaki, H.*; Morinaga, Masahiko*; Kikuchi, Keiichi
Electrochimica Acta, 43(21), p.3235 - 3239, 2002/00
None
Sasajima, Hideo; Fuketa, Toyoshi; Nakamura, Takehiko; Nakamura, Jinichi; Kikuchi, Keiichi*
Journal of Nuclear Science and Technology, 37(5), p.455 - 464, 2000/05
no abstracts in English
Sasajima, Hideo; Fuketa, Toyoshi; Nakamura, Takehiko; Nakamura, Jinichi; Uetsuka, Hiroshi; Kikuchi, Keiichi*; Abe, Tomoyuki*
JAERI-Research 99-060, p.62 - 0, 2000/03
JAERI-Research-99-060.pdf:12.05MB
no abstracts in English
Fuketa, Toyoshi; Nakamura, Takehiko; Sasajima, Hideo; Nagase, Fumihisa; Uetsuka, Hiroshi; Kikuchi, Keiichi*; Abe, Tomoyuki*
Proceedings of an International Topical Meeting on Light Water Reactor Fuel Performance (CD-ROM), 15 Pages, 2000/00
no abstracts in English
Sasajima, Hideo; Fuketa, Toyoshi; Ishijima, Kiyomi; Kikuchi, Keiichi*; Abe, Tomoyuki*
Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00
no abstracts in English
Shibutani, Hideo*; Morinaga, Masahiko*; *; Matsushita, Kenichi*; Kikuchi, Keiichi
Nihon Genshiryoku Gakkai-Shi, 40(6), p.501 - 508, 1998/06
Times Cited Count：2 Percentile：24.49(Nuclear Science & Technology)None
Shibutani, Hideo*; Morinaga, Masahiko*; Kikuchi, Keiichi
Nihon Genshiryoku Gakkai-Shi, 40(1), p.70 - 78, 1998/00
Times Cited Count：4 Percentile：38.68(Nuclear Science & Technology)None
Shibutani, Hideo*; Morinaga, Masahiko*; Kikuchi, Keiichi
Nihon Kinzoku Gakkai-Shi, 62(6), p.534 - 541, 1998/00
None
Kamimura, Katsuichiro; Yano, Soichiro; Kono, Shusaku; Kato, Masato; Morimoto, Kyoichi; Morihira, Masayuki; Kikuchi, Keiichi
PNC TN8410 97-067, 452 Pages, 1997/02
None
Kikuchi, Yasuyuki; Shibata, Keiichi; Asami, Tetsuo; ; *; *
Journal of Nuclear Science and Technology, 22(6), p.499 - 503, 1985/00
Times Cited Count：3 Percentile：53.49(Nuclear Science & Technology)no abstracts in English
Igarashi, Shinichi; Asami, Tetsuo; Kikuchi, Yasuyuki; Nakagawa, Tsuneo; Narita, Tsutomu; Shibata, Keiichi
Nihon Genshiryoku Gakkai-Shi, 26(3), p.191 - 198, 1984/00
Times Cited Count：3 Percentile：38.16(Nuclear Science & Technology)no abstracts in English
Ikusawa, Yoshihisa; Kikuchi, Keiichi; Ozawa, Takayuki; Maeda, Seiichiro; Nakajima, Hiroshi*; Koike, Naoto
no journal, ,
To study the thermal performance of Am-MOX fuels, the high linear power irradiation test with Am-MOX fuels "B14 irradiation test" was carried out in the fast experimental reactor "JOYO". From the result of the irradiation test, the thermal performance for Am-MOX fuel was confirmed and the fuel irradiation behavior code was verified.
Kikuchi, Hideki; Suzuki, Kazuyuki; Sugai, Eiji; Hikita, Keiichi; Otani, Takehisa; Samoto, Hirotaka; Hayashi, Shinichiro
no journal, ,
About 6t the Fugen MOX type B fuels, whose Pu content rate is about 1.7%, were reprocessed on Tokai Reprosessing Plant(TRP) to the present. It was required to control plutonium(Pu) concentration of dissolution liquor because of the higher Pu content of the MOX fuels. There operational method to control Pu concentration by dilution has be established. And the amount of Pu, which was transferred to the highly radioactive liquid waste system with the residue from the clarification process, was investigated.
