Monte Carlo shielding design with a large perturbation calculation method
Author:
Funder
National Key R&D Program of China
Chinese Academy of Sciences
National Natural Science Foundation of China
CAST
HIPS
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference19 articles.
1. ENDF/B-VII. 1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data;Chadwick;Nucl. Data Sheets,2011
2. Depletion calculations based on perturbations. Application to the study of a REP-like assembly at beginning of cycle with TRIPOLI-4®;Dieudonne;Ann. Nucl. Energy,2015
3. Criticality calculations with MCNP4A using correlated sampling methods;Gallmeier;Math. Comput. Simul,1998
4. Review of early 21st-century Monte Carlo perturbation and sensitivity techniques for k-eigenvalue radiation transport calculations;Kiedrowski;Nucl. Sci. Eng.,2017
5. Improvement of fission source distribution by correlated sampling method in Monte Carlo perturbation calculations;Kim;J. Nucl. Sci. Technol.,2018
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