Sensitivity analysis with RELAP5 code using ROSA/LSTF test data on steam generator tube rupture

Takeda, Takeshi; Otsu, Iwao

no journal, , 

Post-test analysis with RELAP5/MOD3.3 code was performed for ROSA/LSTF test on PWR steam generator (SG) tube rupture. The code predicted such main phenomena as different natural circulation between two loops, while it indicated remaining problems in the predictions of broken SG secondary pressure after intact SG depressurization. The sensitivity analysis results found the number of SG tubes with double-ended guillotine break and actuation of high-pressure injection system of emergency core cooling system affect primary and secondary pressures and so forth.