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Konomura, Mamoru
Nihon Genshiryoku Gakkai-Shi ATOMO
, 53(3), p.211 - 214, 2011/03
It is not too much to say that R&D people have common sense to manage incidents in development of FBR with a method of risk analysis. In order to avoid an accident from some incidents, a reactor plant is designed with a way of defense in depth and a concept of multiple function and diversity in the design phase and is constructed and operated with enhancement of its reliability. Actually it is impossible to avoid any mechanical incidents. But the reliability can be enhanced by these incidents with appropriate risk management. In this sense, incidents are valuable for development of FBR. We should pay attention to developer's attitude how he understand incidents and how he improve his system on condition that he keeps transparency of information to public.
Watanabe, Masatoshi; Takeda, Seiji; Maeda, Toshikatsu
no journal, ,
no abstracts in English
Saito, Hironori; Takeda, Seiji; Kimura, Hideo
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Nagasawa, Hirokazu; Takeda, Seiji; Sakai, Ryutaro; Kimura, Hideo
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Chikazawa, Yoshitaka; Kato, Atsushi; Obata, Hiroyuki*
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Maeda, Toshikatsu; Hotta, Katsutoshi*; Usui, Hideo
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Iida, Yoshihisa; Yamaguchi, Tetsuji; Tanaka, Tadao; Nakayama, Shinichi
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Solubility experiments for selenium were performed at high ionic strengths under anoxic conditions. Dominant aqueous selenium species were identified as hydrogen selenide at pH between 5 and 8, and polyselenide at pH between 9 and 13 by UV-Vis absorption spectrometry. A solubility-limiting solid was determined to be amorphous selenium at pH between 5 and 8, and crystalline selenium at pH between 9 and 13. The equilibrium constants and ion interaction coefficients for HSe- and Se42- versus Na+ were determined by specific ion interaction theory.
Obata, Hiroyuki
no journal, ,
We evaluated the amount of the residual sodium on the fuel assembly by using the results of the dry cleaning tests of the fuel assembly mockup. We report the results of the dry cleaning test and the evaluation of the residual sodium on the assembly.
Yanagisawa, Kazuaki
no journal, ,
An influence of fuel core density (2.2, 3.0 and 4.0g/cc) on a fuel failure was studied comparing the silicide fuel (4.8 g/cc) as the reference. (1) The DNB value of the test specimens (below 4.8g/cc) was 175
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C, having no difference to the reference (18014 C). (2) The reference fuel failed at the large temperature drop (larger than 94 C) and the short time to quench (shorter than 0.13s). The test specimens did not fail until 106 cal/g per fuel plate due to the enhanced plasticity of the aluminum matrix. The lower the fuel density, the more the plasticity enhanced. (3) Irrespective to fuel density, the bow was increased with the increasing PCST. Experimental fact revealed that maximum bow at JRR 3 operating (lower than 228 C) is 15% (0.4 mm), where the almost data are within 4% (0.1 mm). (4) For axial permanent strain evaluated by the plate thickness, the test specimens were expanded but the references were shrunk.
Ota, Masakazu; Nagai, Haruyasu
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no abstracts in English
Kr released from the Rokkasho Reprocessing Plant by an atmospheric dispersion model in SPEEDI-MPTerada, Hiroaki; Nagai, Haruyasu; Isogai, Keisuke*; Nitta, Wataru*
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We have been verifying and improving SPEEDI-MP which is a comprehensive prediction system of migration of radionuclides in the atmosphere, ocean, and terrestrial region. In this study, we conducted atmospheric dispersion simulations of radioactive noble gas Kr released from the Rokkasho reprocessing plant for the whole Japan area by using an atmospheric model in SPEEDI-MP, and analyzed significant increases of atmospheric Kr concentration above its background level measured by Japan Chemical Analysis Center. Meteorological fields such as wind field and turbulence were predicted by an atmospheric dynamic model MM5, and atmospheric dispersion of Kr was calculated by a Lagrangian particle dispersion model GEARN. The calculation results agreed well with the measurements of atmospheric Kr concentration at Dazaifu in April 2008 and at Sapporo in September 2008 to confirm the high prediction performance of the model.
Aoyama, Yoshio; Nakagawa, Akinori; Sone, Tomoyuki; Sasaki, Toshiki; Nakazawa, Osamu; Tashiro, Kiyoshi
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Nishio, Katsuhisa; Nishinaka, Ichiro; Mitsuoka, Shinichi; Makii, Hiroyuki; Furutaka, Kazuyoshi; Wakabayashi, Yasuo; Takahashi, Ryuta*; Ishii, Tetsuro; Chiba, Satoshi; Hirose, Kentaro*; et al.
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Aritomo, Yoshihiro; Chiba, Satoshi; Nishio, Katsuhisa
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Funada, Toshio; Suzuki, Mitsutoshi; Senzaki, Masao
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The outline of the collaboration concerning to the plutonium disposition with Russian institutes on vipac fuels and the future plan will be presented in the conference. (one of the four series presentations)
Hosoi, Hideaki*; Yoshida, Hiroyuki
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no abstracts in English
Yoshida, Hiroyuki; Suzuki, Takayuki*; Takase, Kazuyuki; Koizumi, Yasuo*
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Amamoto, Ippei; Fukushima, Mineo; Matsuyama, Kanae*; Okita, Takeshi*; Miyamoto, Shinya*; Utsunomiya, Kazuhiro*; Yano, Tetsuji*
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no abstracts in English
Ikuta, Ryuhei*; Koizumi, Yasuo*; Takase, Kazuyuki
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no abstracts in English
Minato, Futoshi
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no abstracts in English