Sensitivity and uncertainty analysis of neutronic and kinetic parameters for CERCER and CERMET fueled ADS using SERPENT 2 and ENDF/B-VIII.0
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference13 articles.
1. A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT;Aufiero;Ann. Nucl. Energy,2015
2. ENDF/B-VIII.0: the 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data;Brown;Nucl. Data Sheets,2018
3. ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology;Chadwick;Nucl. Data Sheets,2006
4. Nuclear data sensitivity and uncertainty analysis of critical VENUS-F cores with the serpent Monte Carlo code;Fridman;Ann. Nucl. Energy,2020
5. , (last accessed on November 6, 2021).
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