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

Research output: Chapter in Book/Report/Conference proceedingChapter

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.

Original languageEnglish
Title of host publicationTechnical Reports of the Institute of Atomic Energy, Kyoto University
Edition210
Publication statusPublished - Aug 1 1988
Externally publishedYes

ASJC Scopus subject areas

  • Engineering(all)

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    Gofuku, A., Sugano, K., & Wakabayashi, J. (1988). Estimation of break condition at small pipe-break loss-of-coolant-accident of PWR plant using quantitative input-output characteristics of components. In Technical Reports of the Institute of Atomic Energy, Kyoto University (210 ed.)