Applying uncertainty and sensitivity on thermal hydraulic subchannel analysis for the multi-application small light water reactor

Abstract Small modular reactors (SMRs) are a recent advancement in commercial nuclear reactor design with growing interest worldwide. New SMR concepts, such as the Multi-Application Small Light Water Reactor (MASLWR), must undergo a licensing processes established by the U.S. Nuclear Regulatory Commission (NRC) prior to commercial operation. Given the lack of historical, full scale operating experience, a general uncertainty and sensitivity analysis methodology was developed to help aid SMR designs through this process. Uncertainty was quantified through the empirical cumulative distribution function (ECDF) created from a desired data set. Linear regression techniques were applied to measure sensitivity. This methodology was demonstrated through the thermal hydraulic steady-state subchannel analysis of the MASLWR concept using RELAP5-3D Version 4.0.3 and VIPRE-01 Mod 2.2.1. Twelve uncertain input parameters were selected. System response uncertainty in the minimum departure from nucleate boiling ratio (MDNBR), maximum fuel temperature, and maximum clad temperature was evaluated. These figures were shown to satisfy U.S. NRC regulatory requirements for steady state operation at the 95 percent probability and 95 percent confidence level under the evaluated conditions. Sensitivity studies showed input parameters affecting local power generation within the core had a large influence on MDNBR, maximum fuel temperature, and maximum clad temperature.

[1]  Hu Luo Quantified PIRT and uncertainty quantification for computer code validation , 2012 .

[2]  J. Wishart,et al.  Statistics in Research. , 1956 .

[3]  Anh T. Mai Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3 , 2011 .

[4]  Jose N. Reyes,et al.  Testing of the multi-application small light water reactor (MASLWR) passive safety systems , 2007 .

[6]  Giorgio Locatelli,et al.  Financial Case Studies on Small- and Medium-Size Modular Reactors , 2012 .

[7]  Brian Todd Hallee Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method , 2013 .

[8]  L. Wasserman All of Nonparametric Statistics , 2005 .

[9]  Francesco Saverio D'Auria,et al.  Analyses of the OSU-MASLWR Experimental Test Facility , 2012 .

[10]  S. S. Wilks Statistical Prediction with Special Reference to the Problem of Tolerance Limits , 1942 .

[11]  Alexey I. Soldatov Design and analysis of a nuclear reactor core for innovative small light water reactors , 2009 .

[12]  Bradyn J. Wuth Comparative analysis of the Žukauskas method and data from the OSU MASLWR test facility steam generator , 2014 .

[13]  S. S. Wilks Determination of Sample Sizes for Setting Tolerance Limits , 1941 .

[14]  J. C. Chen Correlation for Boiling Heat Transfer to Saturated Fluids in Convective Flow , 1966 .

[15]  Cesare Frepoli,et al.  An Overview of Westinghouse Realistic Large Break LOCA Evaluation Model , 2008 .

[16]  Neil E. Todreas,et al.  Thermal hydraulic fundamentals , 1990 .

[17]  J. C. Chen A Correlation for Boiling Heat Transfer to Saturated Fluids in Convective Flow , 1962 .

[18]  Jon C. Helton,et al.  Survey of sampling-based methods for uncertainty and sensitivity analysis , 2006, Reliab. Eng. Syst. Saf..

[19]  M. Kazimi,et al.  Nuclear Systems II: Elements of Thermal Hydraulic Design , 1990 .

[20]  F. Dittus,et al.  Heat transfer in automobile radiators of the tubular type , 1930 .

[21]  A. Durmayaz,et al.  The 2006 CHF look-up table , 2007 .

[22]  Sung Won Bae,et al.  ANALYSIS OF UNCERTAINTY QUANTIFICATION METHOD BY COMPARING MONTE-CARLO METHOD AND WILKS’ FORMULA , 2014 .

[23]  Feltus,et al.  Statistical core design methodology using the VIPRE thermal-hydraulics code , 1994 .

[24]  R. P. Martin,et al.  AREVA's realistic large break LOCA analysis methodology , 2005 .

[25]  M. Galvin System model of a natural circulation integral test facility , 2009 .

[26]  Francesc Reventos,et al.  Uncertainty and sensitivity analysis of the LOFT L2-5 test: Results of the BEMUSE programme , 2008 .

[27]  Pierre Babka,et al.  Multi-Application Small Light Water Reactor Final Report , 2003 .

[28]  Horst Glaeser,et al.  GRS Method for Uncertainty and Sensitivity Evaluation of Code Results and Applications , 2008 .

[29]  Harold E. Adkins,et al.  Predictive Bias and Sensitivity in NRC Fuel Performance Codes , 2009 .