Published September 1, 2001 | Version v1
Journal article

Intercomparison of results for a PWR rod ejection accident

Description

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 United States, 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

Additional details

Identifiers

PII
S0029549301003752;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
208
Journal Issue
2
Journal Page Range
p. 181-189
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2001 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.