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Journal Articles

Research on core melt accident analysis of LWRs

Abe, Kiyoharu

Tokyo Daigaku Gakui Rombun, 0, 245 Pages, 1994/09

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

Journal Articles

Sensitivity study on PWR source terms with THALES/ART code package and effects of in-vessel thermal-hydraulic models

Abe, Kiyoharu; Watanabe, Norio; Ida, Mitsuo; Sakamoto, Toru; Ishigami, Tsutomu; Harami, Taikan

Proc.on Probabilistic Safety Assessment and Risk Management PSA87, Vol.3, p.945 - 950, 1987/00

no abstracts in English

Journal Articles

Overview of development and application of THALES code system for analyzing progression of core meltdown accident of LWR´s

; *; ; *; *

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operatiions, p.6 - 49, 1986/00

no abstracts in English

Journal Articles

Development of computer code system THALES for thermal-hydrauice analysis of core meltdown accident, I; Outlines of code system and analytical models in each code

; *; Watanabe, Norio; *

Nippon Genshiryoku Gakkai-Shi, 27(11), p.1035 - 1046, 1985/00

 Times Cited Count:1 Percentile:74.87(Nuclear Science & Technology)

no abstracts in English

Journal Articles

PWR S$$_{2}$$D sequence analysis by THALES code system

; *; Watanabe, Norio; ; *

Proc.of ANS/ENS Int.Topical Meeting on Probabilistic Safety Methods and Applications, p.30 - 1, 1985/00

no abstracts in English

JAEA Reports

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