ENDF/B-VIII.0 Augmented Covariance Data The first iteration [Slides]
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Nuclear data are necessary for reliable modeling and simulation of the next generation of nuclear reactors. However, the variation in the ratio of the computed to experimental values (C/E) for certain types of nuclear systems is much less than predicted by evaluated nuclear data file (ENDF)/B covariances. Figure 1 provides an example of a set of metal-plutonium-fueled, fast-spectrum (PU-MET-FAST) integral experiments from the International Criticality Safety Benchmark Evaluation Project (ICSBEP) in the Oak Ridge National Laboratory (ORNL) VALID database. The variation in the C/E values, shown with one standard deviation error bars, is 100% covered by both the SCALE and ENDB/VIII.0 covariance data. This is due to the comparisons to integral data that are essential during the evaluation process. However, the ENDF evaluations represent uncertainties and correlations in differential data only; they do not reflect the impact of the comparison to integral data in the covariance evaluations.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1908354
- Resource Relation:
- Conference: 2019 ANS Winter Meeting & Expo, Washington, DC (United States), 17-21 Nov 2019; Related Information: https://www.ans.org/meetings/view-wm2019/
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
97 MATHEMATICS AND COMPUTING
Nuclear Criticality Safety Program (NCSP)
Nuclear Data
Evaluated Nuclear Data File (ENDF)
International Criticality Safety Benchmark Evaluation Project (ICSBEP)
Covariance Data
Metal-Plutonium-Fueled
Fast-Spectrum (PU-MET-FAST)
Integral Experiments