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JAEA Reports

Uncertainty analyses for HLW disposal system using probabilistic safety assessment code (GSRW-PSA); Parameter uncertainty and conceptual model uncertainty in natural barrier

Takeda, Seiji; Kimura, Hideo

JAERI-Research 2002-014, 20 Pages, 2002/07

JAERI-Research-2002-014.pdf:1.37MB

no abstracts in English

Journal Articles

Confirmatory thermal-hydraulic analyses of safety design concept of a passive safety light water reactor JPSR

Araya, Fumimasa; *; Ochiai, Masaaki

Proc. of Post-SMiRT14 Int. Seminar 18, p.E1.26 - E1.32, 1997/00

no abstracts in English

Journal Articles

Simulation code SAFE for analyzing transient solvent extraction behavior

Maeda, Mitsuru; Fujine, Sachio; *; *

Transactions of the American Nuclear Society, 66, p.78 - 80, 1992/11

no abstracts in English

Journal Articles

Accident analyses for a double-flat-core type HCLWR

Okubo, Tsutomu; Iwamura, Takamichi; *; *; Murao, Yoshio

6th Proc. of Nuclear Thermal Hydraulics, p.79 - 86, 1990/11

no abstracts in English

Journal Articles

Accident analyses for a double-flat-core type HCLWR

Okubo, Tsutomu; Iwamura, Takamichi; *; *; Murao, Yoshio

Transactions of the American Nuclear Society, 62, p.662 - 663, 1990/11

no abstracts in English

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