Abstract
Benchmark calculations for the CE critical experiments were performed by using the 2-dimensional transport code KARMA for which multi-group cross sections and resonance data were prepared by the KAERI library processing procedure. This study includes the 5 CE critical experi- ments performed by Westinghouse. The CE critical experiments consisted of a 30 × 30 square fuel rod array of 2.72 wt% 235U enriched UO2 in zircaloy-2 clad representative of the CE 14 × 14 fuel assembly design. The geometrical bucklings were measured for the 2-dimensional analysis and the fission rate distributions were also measured in the critical experiments. Two different evaluated data libraries including ENDF/B-VI R8 and ENDF/B-VII R0 were used to prepare multi-group cross sections for the KARMA benchmark calculations in order to see the differences between these two libraries. It was shown that the calculated eigenvalues with ENDF/B-VII R0 were much closer to the critical than those with ENDF/B-VI R8, and although the fission rate distribution with ENDF/B-VI R8 is better than those with ENDF/B-VII R0, both fission rate distributions were well predicted when considering the measurement uncertainty.
| Original language | English |
|---|---|
| Pages (from-to) | 1203-1206 |
| Number of pages | 4 |
| Journal | Journal of the Korean Physical Society |
| Volume | 59 |
| Issue number | 23 |
| DOIs | |
| State | Published - Aug 2011 |
| Externally published | Yes |
Keywords
- CE critical
- ENDF
- Transport lattice code
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