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Journal Articles

Simulation of fuel-coolant interaction SERENA2 test based on JASMINE version 3

Hotta, Akitoshi*; Morita, Akinobu*; Kajimoto, Mitsuhiro*; Maruyama, Yu

Nihon Genshiryoku Gakkai Wabun Rombunshi, 16(3), p.139 - 152, 2017/09

Journal Articles

Current trends of thermal-hydraulic research on severe accident

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:10.53(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Uncertainties remaining in severe accident phenomena and related research activities at JAERI

Abe, Kiyoharu; Sugimoto, Jun; *

Reliab. Eng. Syst. Saf., 45, p.3 - 17, 1994/00

 Times Cited Count:1 Percentile:25.79(Engineering, Industrial)

no abstracts in English

Journal Articles

Development of the EWS version of the severe accident analysis code THALES-2

Muramatsu, Ken; *; *; *; *

Dai-6-Kai Kakuritsuronteki Anzen Hyoka (PSA) Ni Kansuru Kokunai Shimpojiumu Rombunshu (IAE-9206), p.171 - 175, 1993/01

no abstracts in English

Journal Articles

Analysis of uncertainty factors on source terms for severe accidents

*; Muramatsu, Ken

Dai-6-Kai Kakuritsuronteki Anzen Hyoka (PSA) Ni Kansuru Kokunai Shimpojiumu Rombunshu (IAE-9206), p.25 - 33, 1993/01

no abstracts in English

Journal Articles

Source term evaluation for small break LOCA sequences at a PWR

Muramatsu, Ken; *

Dai-6-Kai Kakuritsuronteki Anzen Hyoka (PSA) Ni Kansuru Kokunai Shimpojiumu Rombunshu (IAE-9206), p.3 - 8, 1993/01

no abstracts in English

Journal Articles

Analysis of direct containment heating in a BWR Mark-II containment

*; Muramatsu, Ken; *; Sakamoto, Toru*

ANS Proc. of the 1992 National Heat Transfer Conf., p.386 - 400, 1993/00

no abstracts in English

Journal Articles

Comparative study of source terms of a BWR severe accident by THALES-2, STCP and MELCOR

Hidaka, Akihide; *; Soda, Kunihisa; Muramatsu, Ken; Sakamoto, Toru*

ANS Proc. of the 1992 National Heat Transfer Conf., p.408 - 416, 1993/00

no abstracts in English

Journal Articles

The Validation of the ART code through comparison with NSPP experiments in the steam-air atmosphere

*; Muramatsu, Ken

CSNI-R-176, 13 Pages, 1991/00

no abstracts in English

Journal Articles

Analysis of aerosol behavior in containment overpressure failure scenarios in BWR Mark-II plant

*; Watanabe, Norio; *; Muramatsu, Ken

CSNI-R-176, 15 Pages, 1991/00

no abstracts in English

Journal Articles

Development of THALES-2, a computer code for coupled thermal-hydraulics and fission product transport analyes for severe accident at LWRs and its application to analysis of fission product revaporization phenomena

*; Muramatsu, Ken; Watanabe, Norio; *; *

Proc. of the Int. Topical Meeting on Safety of Thermal Reactors, 9 Pages, 1991/00

no abstracts in English

Journal Articles

A New modelling approach for containment event tree construction; Accident progression stage evaent tree method

Watanabe, Norio; *; Muramatsu, Ken

2nd Int. Conf. on Containment Design and Operation,Conf. Proc., Vol. l, 14 Pages, 1990/00

no abstracts in English

Journal Articles

Analysis of NSPP experiment with ART code for analyzing transport behavior of aersol and radionuclide during core meltdown accident

Ishigami, Tsutomu; Kobayashi, Kensuke; *

Nihon Genshiryoku Gakkai-Shi, 31(8), p.920 - 929, 1989/08

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Users manual of ART code for analyzing fissin product transport behaviour during core meltdown accident

Ishigami, Tsutomu; Sakamoto, Toru*; Kobayashi, Kensuke; *

JAERI-M 88-093, 89 Pages, 1988/05

JAERI-M-88-093.pdf:2.2MB

no abstracts in English

Oral presentation

Development of level 3 PSA standard

Homma, Toshimitsu; Kajimoto, Mitsuhiro*; Naito, Makoto*

no journal, , 

no abstracts in English

15 (Records 1-15 displayed on this page)
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