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.
|Title of host publication||Technical Reports of the Institute of Atomic Energy, Kyoto University|
|Publication status||Published - Aug 1 1988|
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