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Tang, P.*; Kita, Kazuyuki*; Igarashi, Yasuhito*; Satou, Yukihiko; Hatanaka, Kotaro*; Adachi, Koji*; Kinase, Takeshi*; Ninomiya, Kazuhiko*; Shinohara, Atsushi*
Progress in Earth and Planetary Science (Internet), 9(1), p.17_1 - 17_15, 2022/03
Times Cited Count：5 Percentile：66.48(Geosciences, Multidisciplinary)Ono, Hitomi*; Takenaka, Keisuke*; Kita, Tomoaki*; Taniguchi, Masashi*; Matsumura, Daiju; Nishihata, Yasuo; Hino, Ryutaro; Reinecke, E.-A.*; Takase, Kazuyuki*; Tanaka, Hirohisa*
E-Journal of Advanced Maintenance (Internet), 11(1), p.40 - 45, 2019/05
Nakamura, Hiroo; Agostini, P.*; Ara, Kuniaki; Cevolani, S.*; Chida, Teruo*; Ciotti, M.*; Fukada, Satoshi*; Furuya, Kazuyuki*; Garin, P.*; Gessii, A.*; et al.
Fusion Engineering and Design, 83(7-9), p.1007 - 1014, 2008/12
Times Cited Count：19 Percentile：75.95(Nuclear Science & Technology)This paper describes the latest design of liquid lithium target system in IFMIF. Design requirement of the Li target is to provide a stable Li jet with a speed of 20 m/s to handle an averaged heat flux of 1 GW/m
. A double reducer nozzle and a concaved flow are applied to the target design. On Li purification, a cold trap and two kinds of hot trap are applied to control impurities below permissible levels. Nitrogen concentration shall be controlled below 10 wppm by one of the hot trap. Tritium concentration shall be controlled below 1 wppm by an yttrium hot trap. To maintain reliable continuous operation, various diagnostics are attached to the target assembly. Among the target assembly, a back-plate made of RAFM is located in the most severe region of neutron irradiation (50 dpa/y). Therefore, two design options of replaceable back wall and their remote handling systems are under investigation.
*; Kukita, Shimpei; Yoshinaka, Kazuyuki; *; *; Shibahara, Itaru*
PNC TN9410 89-190, 48 Pages, 1989/11
None
Suzuki, Kazuyuki; Nakamura, Yoshinobu; Hikita, Keiichi; Kogawa, Takayuki; Hayashi, Shinichiro
no journal, ,
The reprocessing plant dissolves Spent Fuels and it is a process to attract U and Pu after the removal of the Fission Products. Because dissolver is a tank with boiling nitric acid, there is it in the severe corrosion environment. Corrosion environment of the heat transfer surface is the severest. Therefore, the dissolver is made in High Chrome Nickel Steel in consideration of corrosion resistance. This paper reports a supersonic wave measurement method and corrosion rate of the dissolver.
Nakamura, Hiroo; Ida, Mizuho; Miyashita, Makoto; Yoshida, Eiichi; Ara, Kuniaki; Nishitani, Takeo; Okumura, Yoshikazu; Horiike, Hiroshi*; Kondo, Hiroo*; Terai, Takayuki*; et al.
no journal, ,
no abstracts in English
Hikita, Keiichi; Uchida, Naoki; Suzuki, Kazuyuki; Mitani, Hironobu; Hata, Katsuro; Hayashi, Shinichiro; Yudo, Mitsuhiro*; Sakai, Hideaki*
no journal, ,
TRP dissolver deposits dissolver sludge which consists of zircaloy swarf with shearing operation and undissolved fission products such as Mo, Ru, Rh and Pd with dissolution operation. We have developed dissolver cleaning device which can be introduced through a ventilation pipe to inside dissolver.
Sakai, Yusuke*; Akita, Koichi*; Oya, Shinichi*; Sueyoshi, Kazuyuki*; Shobu, Takahisa; Imafuku, Muneyuki*; Suzuki, Kanki*; Iwata, Keiji*
no journal, ,
no abstracts in English
Hata, Katsuro; Suzuki, Kazuyuki; Miyoshi, Ryuta; Sugai, Eiji; Hikita, Keiichi; Nakamura, Yoshinobu; Hayashi, Shinichiro
no journal, ,
The pulse filter of the clarification process used the sintered metal powder filter at Tokai reprocessing plant. It is known that the sintered metal powder filter is easy to be clogged up by sludge. Therefore, we examined the filtration performance of the sintered laminated wire mesh filter which might substitute for the sintered metal powder filter.
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.
Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Ito, Kazuyuki*; Sekita, Satoshi*; Sakamoto, Yukio*; Akutsu, Koichi*
no journal, ,
no abstracts in English
Takeuchi, Masayuki; Sakamoto, Atsushi; Sano, Yuichi; Ito, Kazuyuki*; Sekita, Satoshi*; Sakamoto, Yukio*; Akutsu, Koichi*
no journal, ,
no abstracts in English
Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Ito, Kazuyuki*; Sekita, Satoshi*; Sakamoto, Yukio*; Akutsu, Koichi*
no journal, ,
no abstracts in English
Satou, Yukihiko; Kita, Kazuyuki*; 39 of others*
no journal, ,
no abstracts in English
Kita, Kazuyuki*; Hayashi, Naho; Igarashi, Yasuhito*; Hama, Kenzo*; Zaizen, Yuji*; Sekiyama, Tsuyoshi*; Adachi, Koji*; Yoshida, Naohiro*; Toyoda, Sakae*; Hosaka, Kentaro*; et al.
no journal, ,
no abstracts in English
