Model development for analysis of the Korea advanced liquid metal reactor-Reference-Cited by-同舟云学术

Model development for analysis of the Korea advanced liquid metal reactor

Published:2002-08 Issue:1-2 Volume:217 Page:63-80
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Chang Won-Pyo,Kwon Young-Min,Lee Yong-Bum,Hahn Dohee

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

Reference18 articles.

1. Chang, W.P. et al., 1998. Development of the PSDRS Model for the KALIMER System Analysis Code SSC-K. Korea Atomic Energy Research and Institute, KAERI/TR-1143/98, October 1988.

2. Dunn, F.E. et al., 1974. The SAS2A LMFBR Accident-Analysis Computer Code. ANL-8183, October 1974.

3. Dunn, F.E. et al., 1985. The SASSYS-1 LMFBR Systems Analysis Code. Proceedings of the International Topical Meeting on Fast Reactor Safety, CONF-850410, 999–1006.

4. Greene, G.A., Ginsberg, T., Kazimi, M.S., 1982. Assessment of the Thermal Hydraulic Technology of the Transition Phase of a Core-Disruptive Accident in a LMFBR. US Regulatory Commission, NUREG/CR-3014, November 1982.

5. Guppy, J.G., 1983. Super System Code (SSC, Rev.0) An Advanced Thermo-hydraulic Simulation Code for Transient in LMFBRs. US Nuclear Regulatory Commission, NUREG/CR-3169, April 1983.

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