Development of a physics analysis procedure for the prismatic very high temperature gas-cooled reactors-Reference-Cited by-同舟云学术

Development of a physics analysis procedure for the prismatic very high temperature gas-cooled reactors

Published:2007-11 Issue:11 Volume:34 Page:849-860
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Kim Kang-Seog,Cho Jin-Young,Lee Hyun Chul,Noh Jae Man,Zee Sung Quun

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference16 articles.

1. Breismeister, J.F. et al., 1997. MCNP – A General Monte Carlo N-Particle Transport Code, Version 4B, LA-12625-M.

2. Cho, B.O. et al., 1999. MASTER-2.0: Multi-purpose Analyzer for Static and Transient Effects of Reactors, KAERI/TR-1211/99.

3. Damian, F. et al., 2005. VHTR Neutronic Calculation Scheme: Validation Elemens Using MCNP and TRIPOLI4 Monte-Carlo Codes, M and C 2005, Avignon, France, Sept. 12–15, 2005.

4. Preliminary assessment of lattice physics capabilities for VHTR analysis;Kim;Trans. Am. Nucl. Soc.,2004

5. Reactivity-equivalent physical transformation for elimination of double heterogeneity;Kim;Trans. Am. Nucl. Soc.,2005

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