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Title: LOFA and LOCA analysis on CGNPC SCWR

Abstract

Safety analysis is one of the chief difficulties during the research and design of SCWRs. At present, the development of SCWR safety analysis code is still in the initial stage all around the world, and very few computer codes could carry out trans-critical calculations where significant changes in water properties would take place. In this paper, a safety analysis code SCTRAN for SCWRs, has been developed based on RETRAN-02. The ability of SCTRAN code to simulate the transient where both supercritical and subcritical regimes are encountered has been verified by comparing with APROS code and RELAP5-3D code, respectively. With SCTRAN code, the preliminary LOFA and LOCA analysis of the SCWR design proposed by CGNPC, have been analyzed. The characteristics and performance of the passive safety systems applied to CGNPC-SCWR are evaluated. The results show that: 1) The SCTRAN computer code developed in this study is capable to carry out safety analysis for SCWRs, and its results are reliable; 2) During LOFA and LOCA accidents, very complex flow regime might take place in the double-pass core design, but the passive safety systems would greatly mitigate the consequences of these transients and increase the inherent safety. (authors)

Authors:
; ; ; ;  [1];  [2]
  1. Xi'an Jiaotong Univ., No.28, Xianning West Road, Xi'an, Shaanxi Province (China)
  2. China Nuclear Power Technology Research Inst., Jiangsu Building, Yitian road, Shenzhen, Guangdong Province (China)
Publication Date:
Research Org.:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
22107829
Resource Type:
Conference
Resource Relation:
Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24-28 Jun 2012; Other Information: Country of input: France; 17 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12| 2799 p.
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; COMPUTER CODES; CRITICALITY; DESIGN; LOSS OF COOLANT; NUCLEAR POWER PLANTS; PERFORMANCE; REACTOR SAFETY; SAFETY ANALYSIS; THREE-DIMENSIONAL CALCULATIONS; TRANSIENTS; WATER; WATER COOLED REACTORS

Citation Formats

Wu, P., Gou, J., Shan, J., Jiang, Y., Zhang, B., and Yang, J. LOFA and LOCA analysis on CGNPC SCWR. United States: N. p., 2012. Web.
Wu, P., Gou, J., Shan, J., Jiang, Y., Zhang, B., & Yang, J. LOFA and LOCA analysis on CGNPC SCWR. United States.
Wu, P., Gou, J., Shan, J., Jiang, Y., Zhang, B., and Yang, J. Sun . "LOFA and LOCA analysis on CGNPC SCWR". United States.
@article{osti_22107829,
title = {LOFA and LOCA analysis on CGNPC SCWR},
author = {Wu, P. and Gou, J. and Shan, J. and Jiang, Y. and Zhang, B. and Yang, J.},
abstractNote = {Safety analysis is one of the chief difficulties during the research and design of SCWRs. At present, the development of SCWR safety analysis code is still in the initial stage all around the world, and very few computer codes could carry out trans-critical calculations where significant changes in water properties would take place. In this paper, a safety analysis code SCTRAN for SCWRs, has been developed based on RETRAN-02. The ability of SCTRAN code to simulate the transient where both supercritical and subcritical regimes are encountered has been verified by comparing with APROS code and RELAP5-3D code, respectively. With SCTRAN code, the preliminary LOFA and LOCA analysis of the SCWR design proposed by CGNPC, have been analyzed. The characteristics and performance of the passive safety systems applied to CGNPC-SCWR are evaluated. The results show that: 1) The SCTRAN computer code developed in this study is capable to carry out safety analysis for SCWRs, and its results are reliable; 2) During LOFA and LOCA accidents, very complex flow regime might take place in the double-pass core design, but the passive safety systems would greatly mitigate the consequences of these transients and increase the inherent safety. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2012},
month = {7}
}

Conference:
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