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Hidaka, Akihide*; Kudo, Tamotsu; Kida, Mitsuko; Fuketa, Toyoshi
JAERI-Research 2005-001, 67 Pages, 2005/02
In the VEGA program to investigate radionuclides release from irradiated fuel during severe accidents, the analyses are being performed with VICTORIA2.0 code for comprehensive understanding of radionuclides release and transport phenomena. The VEGA-1 and -3 tests were analyzed in the present study. The correlation for Cs diffusion coefficient in fuel grain obtained from VEGA-1 was applied to the release analysis of VEGA-3. The calculated release of Cs agreed well with the measurement. The correlation was applied to subsequent Cs transport and deposition analyses. The calculation underpredicted the total mass of Cs deposited onto the test apparatuses because nucleation of aerosol and its growth were underestimated due to the consideration of aerosol nucleation originated only from released FP in VICTORIA2.0. A sensitivity analysis with aerosol seeds for heterogeneous nucleation showed a reasonable agreement with the measured Cs distribution. It turned out that additional aerosol seeds besides the released FP be considered when the VICTORIA2.0 code is applied to the VEGA test analyses.
Ishiyama, Shintaro
Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(1), p.106 - 119, 2004/03
To estimate FP deposition rate on the typical turbomachinary including gas turbin of GTHTR300 and exposure dose limit at its maintenance, FP plate-out analysis was been carried out using FP compound formation theory and FP concentration controlled diffusion mechanisum. As the results, following conclusions were derived. (1) It is found that the analysis data computed by the VICTORIA code with assumption of the correct thickness of reactive zone exhibits very good correiation with the experimental data obtained by simulated FP plate-out experiment. (2) Total dose rate and allowable work time at turbin of GTHTR300 are given as 19.2mSv/h and 2.6hours by VICTORIA code analysis.
Yuchi, Yoko; Shibazaki, Hiroaki*; Kudo, Tamotsu; Hidaka, Akihide; Maruyama, Yu; Chino, Eiichi; Nakamura, Hideo; Yoshino, T.*; Suzuki*; Hashimoto, Kazuichiro
JAERI-Conf 2000-015, p.231 - 235, 2000/11
no abstracts in English
Hidaka, Akihide; Maruyama, Yu; Igarashi, Minoru*; Hashimoto, Kazuichiro; Sugimoto, Jun
Nuclear Engineering and Design, 200(1-2), p.303 - 315, 2000/08
Times Cited Count:6 Percentile:42.55(Nuclear Science & Technology)no abstracts in English
Kudo, Tamotsu; Shibazaki, Hiroaki*; Hidaka, Akihide; Maruyama, Yu; Maeda, Akio; Harada, Yuhei; Hashimoto, Kazuichiro; Sugimoto, Jun; Yoshino, T.*; Suzuki, K.*
JAERI-Conf 99-005, p.197 - 201, 1999/07
no abstracts in English
Hidaka, Akihide; Maruyama, Yu; Shibazaki, Hiroaki*; Maeda, Akio; Harada, Yuhei; *; Yoshino, T.*; Sugimoto, Jun
JAERI-Tech 98-026, 83 Pages, 1998/07
no abstracts in English
Hidaka, Akihide; Maruyama, Yu; Igarashi, Minoru*; Hashimoto, Kazuichiro; Sugimoto, Jun
8th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics, 2, p.595 - 604, 1997/00
no abstracts in English
Hidaka, Akihide; Sugimoto, Jun; Muramatsu, Ken; *; *
PSA95: Proc. of Probabilistic Safety Assessment Methodology and Applications, 1, p.241 - 246, 1995/00
no abstracts in English
Shiotsu, Hiroyuki; Ishikawa, Jun; Maruyama, Yu
no journal, ,
no abstracts in English