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Validation of RETRAN-03 by Simulating a Peach Bottom Turbine Trip and Boiloff at the Full Integral Simulation Test Facility

John L. Westacott, Craig E. Peterson, Seung Oh

Nuclear Technology / Volume 100 / Number 2 / November 1992 / Pages 228-245

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34745

The RETRAN-03 computer code is validated by simulating two tests that were performed at the Full Integral Simulation Test (FIST) facility. The RETRAN-03 results of a turbine trip (test 4PTT1) and failure to maintain water level at decay power (test T1QUV) are compared with the FIST test data. The RETRAN-03 analysis of test 4PTT1 is compared with a previous TRAC-BWR analysis of the test. Sensitivity to various model nodalizations and RETRAN-03 slip options are studied by comparing results of test T1QUV. The predicted thermal-hydraulic responses of both tests agree well with the test data. The pressure response of test 4PTT1 and the boiloff rate for test T1QUV are accurately predicted. Core uncovery time is found to be sensitive to the upper downcomer and upper plenum nodalization. The RETRAN-03 algebraic and dynamic slip options produce similar results for test T1QUV.