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Shibata, Masahiro; Sawada, Atsushi; Tachi, Yukio; Hayano, Akira; Makino, Hitoshi; Wakasugi, Keiichiro; Mitsui, Seiichiro; Oda, Chie; Kitamura, Akira; Osawa, Hideaki; et al.
JAEA-Research 2013-037, 455 Pages, 2013/12
Following FY2011, JAEA and NUMO have conducted a collaborative research work which is designed to enhance the methodology of repository design and performance assessment in preliminary investigation stage. With regard to (1) study on rock suitability in terms of hydrology, the tree diagram of methodology of groundwater travel time has been extended for crystalline rock, in addition, tree diagram for sedimentary rock newly has been organized. With regard to (2) study on scenario development, the existing approach has been improved in terms of a practical task, and applied and tested for near field focusing on the buffer. In addition, the uncertainty of some important processes and its impact on safety functions are discussed though analysis. With regard to (3) study on setting radionuclide migration parameters, the approaches for parameter setting have been developed for sorption for rocks and solubility, and applied and tested through parameter setting exercises for key radionuclides.
Nakamura, Takashi*; Kobayashi, Nobuyuki*; Kondo, Yosuke*; Sato, Yoshiteru*; Aoi, Nori*; Baba, Hidetada*; Deguchi, Shigeki*; Fukuda, Naoki*; Gibelin, J.*; Inabe, Naoto*; et al.
Physical Review Letters, 103(26), p.262501_1 - 262501_4, 2009/12
Times Cited Count:198 Percentile:97.53(Physics, Multidisciplinary)no abstracts in English
Deguchi, Akira*; Ohshima, Hiroyuki
JNC TN9400 2003-088, 79 Pages, 2003/03
A detailed thermal-hydraulic analysis computer program SPIRAL is under development for the evaluation of local flow and temperature fields in wire-wrapped fuel pin bundles deformed by the influence of high burn-up, which are hard to reveal by experiment due to measurement difficulty. This report describes the parallelization of SPIRAL for improving applicability to larger numerical simulations. As the parallelization efficiency, approximately twelve times processing speed could be obtained by using 16 processor elements in larger scale simulations.
Ohshima, Hiroyuki; Deguchi, Akira*
JNC TN9400 2003-087, 105 Pages, 2003/03
A thermal-hydraulic analysis computer program ACT is under development for the evaluation of detailed flow and temperature fields in a core region of fast breeder reactors under various operation conditions. The purpose of this program development is to contribute not only to clarifying thermal hydraulic characteristics that cannot be revealed by experiments due to measurement difficulty but also to performing the rational safety design and assessment. This report describes the incorporation of three-dimensional upper plenum model to ACT and its verification study as a part of the program development.
Miyoshi, Yoshinori; Nakajima, Ken; ; Kobayashi, Iwao; Aoki, Shigeaki*; *; *; *
Journal of Nuclear Science and Technology, 31(4), p.335 - 348, 1994/04
Times Cited Count:1 Percentile:17.88(Nuclear Science & Technology)no abstracts in English
Miyoshi, Yoshinori; Nakajima, Ken; Kobayashi, Iwao; Aoki, Shigeaki*; *
Transactions of the American Nuclear Society, 66, p.287 - 288, 1992/11
no abstracts in English
; ; ; ; ; Deguchi, Morimoto
Dai-18-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu, ,
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Ninokata, Hisashi*; Deguchi, Akira*
Numerical-Benchmark Exercise of The Second Inter-national Workshop on Two-Phase Fundamantals, ,
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