AREVA's realistic large break LOCA analysis methodology

The AREVA realistic large break loss-of-coolant-accident (LOCA) analysis methodology received approval by the United States Nuclear Regulatory Commission (USNRC) in April 2003. The methodology references the 1988 amended 10 CFR 50.46 allowing best-estimate calculations of emergency core cooling system performance. In addition, it conforms to the code scaling, applicability, and uncertainty (CSAU) methodology developed by the Technical Program Group for the USNRC in the late 1980s; however, it also incorporates the nonparametric statistical approach originally incorporated in the Gesellschaft fur Anlagen und Reaktorsicherheit (GRS) methodology for LOCA analysis. This paper provides a methodology summary, lessons learned and insight about current LOCA issues.

[1]  F. Akerhielm,et al.  HYDRODYNAMIC AND HEAT TRANSFER MEASUREMENTS ON A FULL-SCALE SIMULATED 36- ROD MARVIKEN FUEL ELEMENT WITH UNIFORM HEAT FLUX DISTRIBUTION. , 1968 .

[2]  L. E. Hochreiter,et al.  THINC-IV: an improved program for thermal-hydraulic analysis of rod bundle cores , 1973 .

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

[4]  D. G. Morris,et al.  Dispersed-flow film boiling in rod-bundle geometry: steady-state heat-transfer data and correlation comparisons. [PWR; BWR] , 1982 .

[5]  Geoffrey F. Hewitt,et al.  Paper 27: Heat Transfer to Steam-Water Mixtures Flowing in Uniformly Heated Tubes in which the Critical Heat Flux has been Exceeded: , 1967 .

[6]  F. J. Moody,et al.  The thermal hydraulics of a boiling water nuclear reactor , 1977 .

[7]  L. J. Finnegan,et al.  CONTEMPT: A COMPUTER PROGRAM FOR PREDICTING THE CONTAINMENT PRESSURE- TEMPERATURE RESPONSE TO A LOSS-OF-COOLANT ACCIDENT. , 1967 .

[8]  Paul N. Somerville.  Tables for Obtaining Non-parametric Tolerance Limits , 1958 .

[9]  R. A. Markley,et al.  Open duct cooling-concept for the radial blanket region of a Fast Breeder reactor , 1971 .

[10]  Lawrence E. Hochreiter,et al.  Application of code scaling applicability and uncertainty methodology to the large break loss of coolant , 1998 .

[11]  K. E. Sackett,et al.  Experiment data report for Semiscale Mod-3 blowdown heat transfer test S-07-2 (baseline test series). [PWR] , 1978 .

[12]  R. J. Miller,et al.  Experimental investigations of uncovered-bundle heat transfer and two-phase mixture-level swell under high-pressure low heat-flux conditions. [PWR] , 1982 .