SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark-Reference-Cited by-同舟云学术

SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark

Published:2015-09 Issue: Volume:83 Page:328-341
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Mercatali L.,Venturini A.,Daeubler M.,Sanchez V.H.

Funder

Program Nuclear Safety Research (NUSAFE)

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference12 articles.

1. ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology;Chadwick;Nucl. Data Sheets,2011

2. Gehin, J.C. et al., 2004. Issues in the Use of Weapons-Grade MOX Fuel in VVER-1000 Nuclear Reactors: Comparison of UO2 and MOX Fuels. ORNL/TM-2004/223.

3. Kalugin, M. et al., 2002. A VVER-1000 LEU and MOX Assembly Computational Benchmark, NEA/NSC/DOC10.

4. Serpent-a Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code;Leppänen,2013

5. VVER-1000 neutronics calculation with ENDF/B-VII data;Mahlers;Ann. Nucl. Energy,2009

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