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 1988
Externally publishedYes

Fingerprint

Loss of coolant accidents
Pressurized water reactors
Pipe
Knowledge representation
Coolants
Enthalpy
Flow rate
Experiments

ASJC Scopus subject areas

  • Engineering(all)

Cite this

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.)

Estimation of break condition at small pipe-break loss-of-coolant-accident of PWR plant using quantitative input-output characteristics of components. / Gofuku, Akio; Sugano, Keiji; Wakabayashi, Jiro.

Technical Reports of the Institute of Atomic Energy, Kyoto University. 210. ed. 1988.

Research output: Chapter in Book/Report/Conference proceedingChapter

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 edn.
Gofuku A, Sugano K, Wakabayashi J. 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. 1988
Gofuku, Akio ; Sugano, Keiji ; Wakabayashi, Jiro. / Estimation of break condition at small pipe-break loss-of-coolant-accident of PWR plant using quantitative input-output characteristics of components. Technical Reports of the Institute of Atomic Energy, Kyoto University. 210. ed. 1988.
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