著者

阿部 清治 西 誠 渡辺 憲夫 工藤 和夫

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌 (ISSN:00047120)

巻号頁・発行日

vol.27, no.11, pp.1035-1046, 1985-11-30 (Released:2009-04-21)

参考文献数

13

被引用文献数

1 2

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THALES is a computer code system for the thermal-hydraulic analysis of the core meltdown accident which is the risk-dominant accident of LWR's. Its first version was developed for the PWR analysis, which uses THALES-P for primary system thermal-hydraulics, THALES-M for core heatup and meltdown, and THALES-CV for containment temperature and pressure response. Several program libraries were also developed not only for THALES but for general usage.A new analysis technique of hydraulics in the primary cooling system was developed and used in THALES-P with aiming at accurate estimation of water level in water-steam mixture and shorter computer time, which are necessary for the core meltdown analysis.This report describes the outlines of the THALES code system, as well as the mathematical modeling and sample run results of the above-mentioned codes. Further are discussed the importance of the mixture levels and the necessity of the core slumping models.

著者

松井 一秋 澤田 隆 山本 章夫 中島 健 阿部 清治 北村 正晴

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会誌ATOMOΣ (ISSN:18822606)

巻号頁・発行日

vol.50, no.5, pp.289-301, 2008 (Released:2019-06-17)

参考文献数

6