Author:
Cui Manman,Guo Yun,Zhang Zhijian
Subject
Nuclear Energy and Engineering
Reference28 articles.
1. Agrawal, A.K., 1978. An Advanced Thermohydraulic Simulation Code for Transients in LMFBRs (SSC-L Code). BNL-NUREG-30773.
2. Primary pipe rupture accident analysis for Clinch River breeder reactor plant;Albright;Nucl. Technol.,1978
3. Alliston, W.H., 1978. Clinch River Breeder Reactor Plant: LMFBR Demo Plant Simulation Model (DEMO). Westinghouse Electric Corporation, Report CRBRP-A2D-0005.
4. Current liquid–metal heat transfer in Japan;Aoki;Prog. Heat Mass Tranfer,1973
5. Model development for analysis of the Korea advanced liquid metal reactor;Chang;Nucl. Eng. Des.,2002
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