Title of article
Intercomparison of results for a PWR rod ejection accident
Author/Authors
Diamond، D.J. نويسنده , , Aronson، A. نويسنده , , Jo، J. نويسنده , , Awakumov، A. نويسنده , , Malofeev، V. نويسنده , , Sidorov، V. نويسنده , , Ferraresi، P. نويسنده , , Gouin، C. نويسنده , , Aniel، S. نويسنده , , Royer، M.E. نويسنده ,
Issue Information
دوهفته نامه با شماره پیاپی سال 2001
Pages
-180
From page
181
To page
0
Abstract
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.
Keywords
Power stations , Power plants , Plant life management
Journal title
Nuclear Engineering and Design
Serial Year
2001
Journal title
Nuclear Engineering and Design
Record number
13725
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