Author:
Lim Changhyun,Joo Han Gyu,Yang Won Sik
Funder
Korea Foundation Of Nuclear Safety
Nuclear Safety and Security Commission
Seoul National University
Subject
Nuclear Energy and Engineering
Reference23 articles.
1. Overall system description and safety characteristics of prototype gen IV sodium cooled fast reactor in Korea;Yoo;Nuclear Eng. Technol.,2016
2. Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers;Jung;Ann. Nuclear Energy,2013
3. Fast reactor physics and computational methods;Yang;Nuclear Eng. Technol.,2017
4. ZZ KAFAX-E70, 150 and 12 groups cross section library in MATXS format based on ENDF/B-VII.0 for fast reactors;Gil,2009
5. ETOE-2/MC2–2/SDX multi-group cross-section processing;Toppel,1978
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