Production of Multigroup data covariance in the resonance range by Monte-Carlo calculations
Conference
·
OSTI ID:22039654
- CEA/Cadarache, 13108 Saint-Paul-Lez Durance (France)
- EC-JRC-IRMM, Retieseweg 111, B-2440 Geel (Belgium)
The generation of Multi-group cross sections together with relevant uncertainties is fundamental to assess the quality of neutronic simulations. Key information that are needed to propagate the microscopic experimental uncertainties up to macroscopic reactor calculations are (1) the experimental covariance matrices, (2) the correlations between the parameters of the model and (3) the multi-group covariance matrices. This work proposes to apply a Monte-Carlo approach to provide explicit data covariances between the resonance parameters. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 22039654
- Country of Publication:
- United States
- Language:
- English
Similar Records
On the Methodology to Calculate the Covariance of Estimated Resonance Parameters
“Full Model” Nuclear Data and Covariance Evaluation Process Using TALYS, Total Monte Carlo and Backward-forward Monte Carlo
Nuclear Data Uncertainty Quantification for Adjoint-Weighted Quantities via XGPT in Monte Carlo Codes
Journal Article
·
Wed Jan 14 23:00:00 EST 2015
· Nuclear Data Sheets
·
OSTI ID:22436778
“Full Model” Nuclear Data and Covariance Evaluation Process Using TALYS, Total Monte Carlo and Backward-forward Monte Carlo
Journal Article
·
Wed Jan 14 23:00:00 EST 2015
· Nuclear Data Sheets
·
OSTI ID:22436783
Nuclear Data Uncertainty Quantification for Adjoint-Weighted Quantities via XGPT in Monte Carlo Codes
Journal Article
·
Wed Jun 15 00:00:00 EDT 2016
· Transactions of the American Nuclear Society
·
OSTI ID:22991922