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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

High pressure pool scrubbing experiment for a PWR severe accident

Hashimoto, Kazuichiro; Soda, Kunihisa; Uno, Seiichiro

Proc. of the Int. Topical Meeting on Safety of Thermal Reactors, p.740 - 745, 1991/00

no abstracts in English

Journal Articles

User effects on RELAP5/MOD2 analysis of ROSA-IV/LSTF cold-leg break LOCA experiment

Watanabe, Tadashi; Kukita, Yutaka; *

Proc. of the Int. Topical Meeting on Safety of Thermal Reactors, p.349 - 357, 1991/00

no abstracts in English

Journal Articles

Loss of residual heat removal(RHR) during PWR MID-loop operation; Experiments in ROSA-IV/LSTF

Nakamura, Hideo; Anoda, Yoshinari; Kukita, Yutaka

Proc. of the Int. Topical Meeting on Safety of Thermal Reactors, p.497 - 503, 1991/00

no abstracts in English

Journal Articles

CCFL characteristics of PWR steam generator U-tubes

Yonomoto, Taisuke; Anoda, Yoshinari; Kukita, Yutaka; Y.Peng*

Proc. of the Int. Topical Meeting on Safety of Thermal Reactors, p.522 - 529, 1991/00

no abstracts in English

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