This study uses the RELAP4/MOD5 Computer Code to analyze the effects of critical flow modeling on the thermal-hydraulic transient response of a General Electric boiling water reactor to a major primary coolant line rupture. Included is a presentation of the equations, assumptions, and limitations of the critical flow models available for use in RFLAP4. Additionally, an evaluation of a temporary solution to a RELAP4 coding error associated with stagnation properties ...
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