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Ando, Masaki; Fukushima, Masahiro; Okajima, Shigeaki; Yamamoto, Toru*; Ando, Yoshihira*
no journal, ,
Evaluation of the Doppler reactivity effect of MOX fueled LWR is planned and being carried out using FCA. In this presentation, the scope of the plan is introduced, and the results of the first experiment using uranium samples in a uranium fueled core and the analysis is reported. The result of the analysis using the JENDL-3.3 library and FCA's code system showed good agreement with the measured values.
Kokubu, Yoko; Suzuki, Daisuke; Lee, C. G.; Magara, Masaaki; Kimura, Takaumi; Shinohara, Nobuo
no journal, ,
no abstracts in English
Fujiwara, Takeshi; Terunuma, Naohiro; Nakayama, Shinichi
no journal, ,
Sr-90 and Cs-137 are the main nuclides of heat generation in the high-level radioactive waste. To improve the flexibility of the disposal site design by attenuating the calorific value of the nuclides of heat generation, the evaluation of characteristics of waste including the nuclides of heat generation is advanced. The absorption method with the inorganic ion-exchangers is proposed as one of the methods of collecting the nuclides of heat generation. The inorganic ion-exchangers that adsorbed Sr and Cs became Sr-Cs sintered compact by heating it under pressurizing with a hot press device and its volume was less than half of initial inorganic ion-exchangers. It became an inhomogeneous sintered compact when the zeolite was contained. A homogeneous sintered compact was obtained when consisting only of the titanic acid.
Yanagisawa, Kazuaki
no journal, ,
By using a mini-plate fuel (density 4.8g per cc) as a simulation of JMTR silicide fuel plate, in-core irradiation test postulating an abnormal withdrawal of control rod during reactor start-up was performed. Because a peak cladding surface temperature predicted by EURECA computer code for JMTR safety calculation is 110
C in maximum, more severe condition is imposed on in-core tested mini-plate fuel, where a peak cladding surface temperature is as high as 137C. It is revealed from post-irradiation examination that the tested mini-plate fuel was intact. From this experimental fact, it is found that JMTR silicide fuel plate has a safety margin against an abnormal withdrawal of control rod during reactor start-up.
Yamano, Hidemasa; Tobita, Yoshiharu
no journal, ,
In this study, experimental analyses suitable for the verification of the COMPASS code were performed using the SIMMER-III code, and provided a boundary condition for the integral verification of the COMPASS code.
Watanabe, Yoko; Kawasaki, Masatsugu
no journal, ,
no abstracts in English
Shimada, Taro; Uno, Yuichi*; Tanaka, Tadao; Nakayama, Shinichi
no journal, ,
no abstracts in English
MoO
-NaMoO eutecticNagai, Takayuki; Fukushima, Mineo; Myochin, Munetaka; Uehara, Akihiro*; Yamana, Hajimu*
no journal, ,
The cyclic voltammetry was carried out in the molten LiMoO-NaMoO eutectic and it was confirmed that the potential window in this melt is smaller than that in molten chloride. After dissolution of UO powder into the molten LiMoO-NaMoO eutectic, the redox reaction of dissolved uranium in the melt were observed by the cyclic voltammetry.
Shikaze, Yoshiaki; Tanimura, Yoshihiko; Saegusa, Jun; Tsutsumi, Masahiro; Uchita, Yoshiaki; Yoshizawa, Michio
no journal, ,
no abstracts in English
Nakama, Shigeo; Fujita, Tomoo
no journal, ,
no abstracts in English
Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Kitagaki, Toru; Washiya, Tadahiro; Kobayashi, Tsuguyuki*; Tasaka, Masayuki*
no journal, ,
no abstracts in English
Hirose, Takanori; Tanigawa, Hiroyasu; Enoeda, Mikio; Kawahito, Yosuke*; Serizawa, Hisashi*; Katayama, Seiji*
no journal, ,
no abstracts in English
Yamane, Yuichi
no journal, ,
An Approximate expression was developed for the power profile and released fission energy in the monotonic decrease after the first peak of the power profile in criticality accident with nuclear fuel solution. The evaluation using it showed good agreement with the experimental result of TRACY.
Shimada, Asako; Haraga, Tomoko; Kameo, Yutaka; Nakashima, Mikio; Takahashi, Kuniaki
no journal, ,
Extraction chromatography technique was applied to analysis of alpha nuclides stuck on surface of stainless steel. Firstly, the surface of stainless steel was dissolved with mixed acid (nitric acid: hydrochloric acid: water = 1:1:4), and then Th and U or Pu and Am were spiked. These solutions were introduced into UTEVA or TRU resins and alpha nuclides were separated. All of the experimented nuclides were recovered in the expected fractions and these recovery percents were over 80%. These methods were applied to analysis of alpha nuclides in pipings of cooling system of Fugen power plant, Advanced Thermal Reactor.
Okuno, Hiroshi; Tonoike, Kotaro; Kawasaki, Hiromitsu*
no journal, ,
no abstracts in English
Yano, Kimihiko; Washiya, Tadahiro; Kase, Takeshi; Nakajima, Yasuo; Chikazawa, Takahiro*; Kikuchi, Toshiaki*
no journal, ,
For uranyl nitrate hexahydrate including barium nitrate as a solid impurity, Washing Experiment was carried out with the decorne type filtering centrifuge. The decontamination effect by washing and spin-drying was confilmed.
Yoshida, Hiroyuki; Suzuki, Takayuki*; Takase, Kazuyuki; Koizumi, Yasuo*
no journal, ,
no abstracts in English
Ikuta, Ryuhei*; Koizumi, Yasuo*; Takase, Kazuyuki
no journal, ,
no abstracts in English
Takamine, Jun; Haruyama, Mitsuo; Takase, Misao
no journal, ,
no abstracts in English