Author:
Lyu Siyu,Lu Daogang,Sui Danting
Funder
National Natural Science Foundation of China
Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference6 articles.
1. Development and application of a safety analysis code for small Lead cooled Fast Reactor SVBR 75/100;Guo;Ann. Nucl. Energy,2015
2. Development of three-dimensional hot pool model in a system analysis code for pool-type FBR;Sui;Nucl. Eng. Des.,1970
3. D. Sui, D. Lu, C. Guo, X. Zhang, L. Tian, and X. Qian, “Development of passive direct reactor auxiliary cooling system model in Liquid Metal Fast Breeder Reactor,” ICMREE 2013 - Proc. 2013 Int. Conf. Mater. Renew. Energy Environ., vol. 3, pp. 880–884, 2013.
4. SAC-CFR computer code verification with Experimental Breeder Reactor II loss-of-primary-flow-without-scram tests data;Guo;Ann. Nucl. Energy,2014
5. N. E. Division, 2012. “Benchmark Specifications and Data Requirements for EBR-II Shutdown Heat Removal Tests SHRT-17 and SHRT-45R.”.
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