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Herranz, L. E.*; Jacquemain, D.*; Nitheanandan, T.*; Sandberg, N.*; Barr
, F.*; Bechta, S.*; Choi, K.-Y.*; D'Auria, F.*; Lee, R.*; Nakamura, Hideo
Progress in Nuclear Energy, 127, p.103432_1 - 103432_14, 2020/09
Times Cited Count：7 Percentile：22.52(Nuclear Science & Technology)Yoshizawa, Atsufumi*; Oba, Kyoko; Kitamura, Masaharu*
Nihon Kikai Gakkai Rombunshu (Internet), 83(856), p.17-00263_1 - 17-00263_17, 2017/12
Ishikawa, Jun; Muramatsu, Ken; Sakamoto, Toru*
JAERI-Research 2005-021, 133 Pages, 2005/09
JAERI-Research-2005-021.pdf:7.58MB
The THALES-2 code is an integrated severe accident analysis code in order to simulate the accident progression and transport of radioactive material for probabilistic safety assessment (PSA) of a nuclear power plant, a part of a level 3 PSA being performed at JAERI for a 1,100MWe BWR-5 with a Mark-II containment. Results and insights from the analyses were that (1) the calculated release fractions of CsI and CsOH to the environment were in the range of 0.01 to 0.1 for late containment overpressure failure cases, and the release fractions for the containment venting case were one order of magnitude smaller than that of over-pressure case and those for drywell spray recovery cases where no containment failure occurred were two orders of magnitude smaller than the containment venting cases, (2) the governing factors for source terms of Iodine and Cesium are different depending on whether the containment fails before core melt or not, (3) the containment venting, which is one of the accident management measures, can be expected to reduce source terms if suppression pool bypass is avoided.
Suzuki, Mitsuhiro
JAERI-Review 2004-013, 123 Pages, 2004/05
JAERI-Review-2004-013.pdf:6.62MB
no abstracts in English
Sugimoto, Jun
JAERI-Conf 99-005, 523 Pages, 1999/07
no abstracts in English
Sugimoto, Jun
JAERI-Conf 98-009, 501 Pages, 1998/05
no abstracts in English
21, 1997, Tokai-mura, Japan; ; Sugimoto, Jun
JAERI-Conf 97-011, 829 Pages, 1998/01
no abstracts in English
Sugimoto, Jun; Hashimoto, Kazuichiro*; Yamano, Norihiro; Hidaka, Akihide; Maruyama, Yu; Uetsuka, Hiroshi; Fuketa, Toyoshi; Nakamura, Takehiko; Soda, Kunihisa; Katanishi, Shoji*
Nihon Genshiryoku Gakkai-Shi, 39(2), p.123 - 134, 1997/02
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)no abstracts in English
Nariai, Hideki*; Sugiyama, Kenichiro*; Kataoka, Isao*; Mishima, Kaichiro*; ; Monde, Masanori*; Sugimoto, Jun; ; Hidaka, Akihide; ; et al.
Nihon Genshiryoku Gakkai-Shi, 39(9), p.739 - 752, 1997/00
Times Cited Count：1 Percentile：8.11(Nuclear Science & Technology)no abstracts in English
; Sugimoto, Jun
Nihon Genshiryoku Gakkai-Shi, 39(4), p.46 - 47, 1997/00
no abstracts in English
Sugimoto, Jun
Heat and Mass Transfer in Severe Nuclear Reactor Accidents, 0, p.462 - 477, 1996/00
no abstracts in English
Sugimoto, Jun
Dennetsu Kenkyu, 34(133), p.52 - 59, 1995/04
no abstracts in English
Soda, Kunihisa; Kukita, Yutaka; ; Sugimoto, Jun; Yamano, N.
Int. Conf. on New Trends in Nuclear System Thermohydraulics,Proc,Vol. II, 0, p.3 - 8, 1994/00
no abstracts in English
Sugimoto, Jun; Yamano, N.; Maruyama, Yu; Kudo, Tamotsu; Soda, Kunihisa
Safety Options for Future Pressurized Water Reactors, 0, 14 Pages, 1994/00
no abstracts in English
Sugimoto, Jun; Yamano, N.; Maruyama, Yu; Hidaka, Akihide; Soda, Kunihisa
JAERI-M 92-035, 20 Pages, 1992/03
no abstracts in English
Soda, Kunihisa; Sugimoto, Jun; Yamano, N.; Shiba, Koreyuki
NUREG/CP-0118, p.12-7 - 12-8, 1991/00
no abstracts in English
Nakamura, Hideo
no journal, ,
no abstracts in English
Nakamura, Hideo
no journal, ,
no abstracts in English
