Abstract
We performed a 3-dimensional CFD analysis of a natural convective flow in the steam generator (SG) inlet plenum of an optimized power reactor 1000 MWe (OPR1000) to generate input parameters of the MELCOR code, a 1-dimensional lumped parameter code, which will be used in analyzing the temperature induced steam generator tube rupture (TI-SGTR) accident. The input parameters used in the MELCOR calculation will account for a 3-dimensional effect in the natural convective flow in the SG inlet plenum. To produce a credible CFD analysis result, we first established a CFD analysis methodology, which is developed from validation analyses against the steam generator design data of the OPR1000 and the Westinghouse 1/7 scaled-down test data, for the thermal mixing flow calculation between the SG and the reactor pressure vessel in the OPR1000. Though this CFD analysis, we produced the MELCOR input parameters, the recirculation ratio 1.96, thermal mixing fraction 0.79, discharge coefficient 0.13, and hot tube fraction 0.40, with an error range of approximately 10% to 25%. The input parameters will be used in the MELCOR analysis to evaluate a radioactive material release from broken SG tubes during the TI-SGTR accident.
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