INTERCOMPARISON OF RESULTS FOR A PWR ROD EJECTION ACCIDENT

Conference · Fri Oct 01 04:00:00 EDT 1999

OSTI ID:759033

DIAMOND, D J ^[1]; ARONSON, A; JO, J; AVVAKUMOV, A; MALOFEEV, V; SIDOROV, V; FERRARESI, P; GOUIN, C; ANIEL, S; ROYER, M E

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1. BROOKHAVEN NATIONAL LABORATORY

This study is part of an overall program to understand the uncertainty in best-estimate calculations of the local fuel enthalpy during the rod ejection accident. Local fuel enthalpy is used as the acceptance criterion for this design-basis event and can also be used to estimate fuel damage for the purpose of determining radiological consequences. The study used results from neutron kinetics models in PARCS, BARS, and CRONOS2, codes developed in the US, the Russian Federation, and France, respectively. Since BARS uses a heterogeneous representation of the fuel assembly as opposed to the homogeneous representations in PARCS and CRONOS, the effect of the intercomparison was primarily to compare different intra-assembly models. Quantitative comparisons for core power, reactivity, assembly fuel enthalpy and pin power were carried out. In general the agreement between methods was very good providing additional confidence in the codes and providing a starting point for a quantitative assessment of the uncertainty in calculated fuel enthalpy using best-estimate methods.

• Research Organization: Brookhaven National Lab., Upton, NY (US)
• Sponsoring Organization: Nuclear Regulatory Commission (US)
• DOE Contract Number: AC02-98CH10886
• OSTI ID: 759033
• Report Number(s): BNL--NUREG-67156; 401001060; 401001060
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
COMPUTERIZED SIMULATION
DATA COVARIANCES
ENTHALPY
NUCLEAR FUELS
PWR TYPE REACTORS
REACTIVITY
ROD EJECTION ACCIDENTS