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RELAP5 code study of ROSA/LSTF validation tests for PWR safety system using SG secondary-side depressurization

蒸気発生器二次側減圧を利用したPWR安全システムに関するROSA/LSTF検証実験のRELAP5コードによる解析的研究

竹田 武司 ; 大貫 晃*; 西 弘昭*

Takeda, Takeshi; Onuki, Akira*; Nishi, Hiroaki*

RELAP5 code post-test analyses were performed on two ROSA/LSTF validation tests for PWR safety system that simulated cold leg small-break LOCAs using SG secondary-side depressurization. The SG depressurization was initiated by fully opening the depressurization valves a little after a safety injection signal. In the 8-in. break test, core uncovery and heatup took place by boil-off. Core collapsed liquid level recovered after accumulator coolant injection. In the 4-in. break test, no core uncovery and heatup happened. Adjustment of break discharge coefficient for two-phase discharge flow predicted the break flow rate reasonably well. The code overpredicted the peak cladding temperature (PCT) because of underprediction of the core collapsed liquid level in the 8-in. break case. Sensitivity analyses indicated that a time delay for SG depressurization start and break discharge coefficient for two-phase discharge flow affect the PCT significantly in the 8-in. break case.

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