Validation the Monte Carlo code RMC with C5G7 benchmark-Reference-Cited by-同舟云学术

Validation the Monte Carlo code RMC with C5G7 benchmark

Published:2013-12 Issue: Volume:265 Page:64-68
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Gao B.,Ma X.B.,Chen Y.X.,Yu H.

Funder

National Natural Science Foundation of China

National science and Technology Major Project

Program for New Century Excellent Talents in University

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference13 articles.

1. Status of the VIM Monte Carlo Neutron/Photon Transport Code;Blomquist,2002

2. SCALE 5: Powerful New Criticality Safety Analysis Tools;Bowman,2003

3. Progress on RMC – a Monte Carlo neutron transport code for reactor analysis;Kan,2011

4. A New Assembly-level Monte Carlo Neutron Transport Code for Reactor Physics Calculations, Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications;Jaakko Leppänen,2005

5. Using various point wise and multi-group cross section libraries in MORET criticality calculations;Miss,2007

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