VERA-CS (Virtual Environment for Reactor Applications, Core Simulator) is a coupled neutron transport and thermal-hydraulics code under development by the Conscirtium for Advanced Simulation of Light Water Reactors (CASL). An approach to uncertainty quantification and sensitivity analysis with VERA-CS was developed and a new toolkit was created to perform uncertainty quantification and sensitivity analysis. A 2 x 2 fuel assembly model was developed and Simulated by VERA-CS, and uncertainty quantification and Sensitivity analysis were performed with fourteen uncertain. input parameters. The minimum departure from nucleate boiling ratio (MDNBR), maximum fuel center-line temperature, and maximum outer clad surface temperature were chosen as the selected figures of merit. Pearson, Spearman, and partial correlation coefficients were considered for all of the figures of merit in sensitivity analysis and coolant inlet temperature was consistently the most influential parameter. Parameters used as inputs to the critical heat flux calculation with the W-3 correlation were shown to be the most influential on the MDNBR, maximum fuel center-line temperature, and maximum outer clad surface temperature. (C) 2016 Elsevier Ltd. All rights reserved.
机构:
Utah State Univ, Dept Mech & Aerosp Engn, Old Main Hill, Logan, UT 84322 USAUtah State Univ, Dept Mech & Aerosp Engn, Old Main Hill, Logan, UT 84322 USA
机构:
Univ Pittsburgh, Dept Mech Engn & Mat Sci, 3700 OHara St, Pittsburgh, PA 15261 USAUtah State Univ, Dept Mech & Aerosp Engn, Old Main Hill, Logan, UT 84322 USA
Ban, Heng
Szilard, Ronaldo
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Idaho Natl Lab, 2525 Fremont Ave, Idaho Falls, ID 83415 USAUtah State Univ, Dept Mech & Aerosp Engn, Old Main Hill, Logan, UT 84322 USA