Estimation of break condition at small pipe-break loss-of-coolant-accident of PWR plant using quantitative input-output characteristics of components

Akio Gofuku; Keiji Sugano; Jiro Wakabayashi

Estimation of break condition at small pipe-break loss-of-coolant-accident of PWR plant using quantitative input-output characteristics of components

Akio Gofuku
, Keiji Sugano
, Jiro Wakabayashi

研究成果

抄録

Quantitative representations of input-output characteristics for both flow rate and specific enthalpy of coolant in the components of PWR (Pressurized Water Reactor) primary side are derived based on a simple PWR primary side model. An estimation technique of break condition at small pipe-break loss-of-coolant-accident is proposed using the quantitative knowledge representations. The applicable break size of the technique is considered as 0.05 to 0.25 ft² (4.64×10^-3 to 2.32×10^-2m²) by the results of several computer experiments, where the reference data are obtained using a safety analysis code RELAP4/MOD6.

本文言語	English
ホスト出版物のタイトル	Technical Reports of the Institute of Atomic Energy, Kyoto University
版	210
出版ステータス	Published - 8月 1988
外部発表	はい

ASJC Scopus subject areas

工学一般

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引用スタイル

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abstract = "Quantitative representations of input-output characteristics for both flow rate and specific enthalpy of coolant in the components of PWR (Pressurized Water Reactor) primary side are derived based on a simple PWR primary side model. An estimation technique of break condition at small pipe-break loss-of-coolant-accident is proposed using the quantitative knowledge representations. The applicable break size of the technique is considered as 0.05 to 0.25 ft2 (4.64×10-3 to 2.32×10-2m2) by the results of several computer experiments, where the reference data are obtained using a safety analysis code RELAP4/MOD6.",

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