Nuclear data uncertainty for criticality-safety: Monte Carlo vs. linear perturbation-Reference-Cited by-同舟云学术

Nuclear data uncertainty for criticality-safety: Monte Carlo vs. linear perturbation

Published:2016-06 Issue: Volume:92 Page:150-160
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Rochman D.,Vasiliev A.,Ferroukhi H.,Zhu T.,van der Marck S.C.,Koning A.J.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference21 articles.

1. ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data

2. UO2 versus MOX: Propagated Nuclear Data Uncertainty for keff, with Burnup

3. International Handbook of evaluated criticality-safety benchmark experiments, September 2010 Edition. OECD/NEA Nuclear Science Committee, NEA/NSC/DOC(95)03.

4. Kiedrowski, B.C., 2013. MCNP6.1 k-Eigenvalue sensitivity capability: a user’s guide, LA-UR-13-22251, Los Alamos National Laboratory.

5. Modern Nuclear Data Evaluation with the TALYS Code System

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