Abstract
New isotopic depletion capabilities and ENDF/B-VII data libraries have been implemented in the recent release 6.1 of SCALE, a comprehensive modeling and simulation suite for nuclear safety analysis and design developed and maintained by Oak Ridge National Laboratory. An assessment of the effect of the new developments on the code performance is the subject of this paper. The analysis is focused on evaluating the code performance in predicting isotopic compositions in spent nuclear fuel by using an extensive, measured isotopic assay database. The analysis results obtained using the latest ENDF/B-VII cross-section data and different resonance processing methods in SCALE are compared to the results of previous validation studies that used ENDF/B-V data. The performance of SCALE depletion capabilities with respect to other computational systems is assessed based on recent published results that were obtained using ENDF/B-VII libraries.
| Original language | English |
|---|---|
| Pages (from-to) | 43-55 |
| Number of pages | 13 |
| Journal | Annals of Nuclear Energy |
| Volume | 46 |
| DOIs | |
| State | Published - Aug 2012 |
Funding
The authors acknowledge the funding from the US Nuclear Regulatory Commission Office of Nuclear Regulatory Research and the US Department of Energy Office of Nuclear Energy for the work described in this paper. Oak Ridge National Laboratory is managed by UT-Battelle, LLC, under Contract DE-AC05-00OR22725 with the US Department of Energy.
Keywords
- Depletion
- ENDF/B-VII
- Isotopic validation
- ORIGEN
- SCALE
- Spent fuel