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Takahashi, Naoki; Suzuki, Soju; Saito, Hiroto; Ueno, Takashi; Abe, Sadayoshi; Yamanaka, Atsushi; Tanigawa, Masafumi; Nakamura, Daishi; Sasaki, Shunichi; Mine, Tadaharu
Nihon Genshiryoku Gakkai Homu Peji (Internet), 20 Pages, 2017/05
no abstracts in English
Numata, Shinji; Hata, Katsuro; Nakamura, Daishi; Miyoshi, Ryuta; Wakimoto, Fumitsugu; Taguchi, Katsuya
no journal, ,
no abstracts in English
Otani, Takehisa; Suzuki, Kazuyuki; Hata, Katsuro; Kikuchi, Hideki; Nakamura, Daishi; Samoto, Hirotaka; Tanaka, Yukiyoshi
no journal, ,
The investigation of the behavior of krypton gas arising due to reprocessing of spent fuels has been performed at TRP. The whole amount of Kr gas transfers to the off-gas system through shearing and dissolution process, so it is applicable as an indicator to determine the progress of fuel dissolution. It is thought that the behavior of gaseous fission product, including Kr, in the spent fuels depends on burn-up and the type of spent fuels. In the reprocessing process, these deference are reflected to the migration rate of krypton gas between shearing off-gas system (SOG) and dissolver off-gas system (DOG). At TRP, four types of spent fuels (LWR; PWR, BWR and ATR; UO
, MOX) were treated and examined about their release characteristics of krypton gas in order to understand the effect on burn-up and type of spent fuels. In this report, the results concerning the ATR-UO fuel and ATR-MOX fuel are discussed compared with the results of LWR fuel.
Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Iuchi, Hiroshi; Tokoro, Daishiro*; Kanemura, Takuji; Ida, Mizuho; Watanabe, Kazuyoshi; Niitsuma, Shigeto; Wakai, Eiichi; et al.
no journal, ,
Engineering Validation and Engineering Design Activities (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) were started from July 2007 under an international agreement called ITER Broader Approach. As a major Japanese activity, EVEDA Li test loop (ELTL) to simulate hydraulic and impurity conditions of IFMIF has already designed and is under construction, in which feasibility of hydraulic stability of the liquid Li target, the purification systems of hot traps are major key issues to be validated in this loop. This presentation focuses on the engineering design of the ELTL, and its construction and commissioning.
Nakamura, Daishi; Kikuchi, Hideki; Terunuma, Hirotaka; Uchida, Naoki; Tanaka, Yukiyoshi
no journal, ,
Sludge generated in the dissolution vessel deposit on storage vessel and caused translation pipe to be choked. It is difficult to remove sludge from vessel and translation piping for few of accessible point in this line and high radioactive environment. In this report, we report on the blockage removal device and method in translation piping adapted on existing machine in order to establish sludge removal technique.
Numata, Shinji; Isomae, Hidemi; Omura, Masami; Tsutagi, Koichi; Kobayashi, Daisuke; Nakamura, Daishi; Nemoto, Masahiro; Iida, Masayoshi*; Tajiri, Kazuma*; Kurita, Tsutomu
no journal, ,
no abstracts in English