Loss of Flow Analysis of Maanshan Nuclear Power Plant With RELAP5/SNAP (NUREG/IA-0483)

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Publication Information

Manuscript Completed: May 2017
Date Published: October 2018

Prepared by:
Chunkuan Shih, Jong-Rong Wang, Shao-Wen Chen, Jian-Ting Chen, Yuh-Ming Ferng, Ting-Yi Wang*, Hsien-Lang Chiu*

Nuclear and New Energy Education and Research Foundation
Institute of Nuclear Engineering and Science, National Tsing Hua University
101 Section 2, Kuang Fu Rd., HsinChu, Taiwan

*Department of Nuclear Safety, Taiwan Power Company
242, Section 3, Roosevelt Rd., Zhongzheng District, Taipei, Taiwan

K. Tien, NRC Project Manager

Division of Systems Analysis
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Prepared as part of:
The Agreement on Research Participation and Technical Exchange
Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

Published by:
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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Abstract

The objective of this study is to assess the applicability of the RELAP5/MOD3.3 model of Maanshan NPP on Loss of Flow transient. Maanshan NPP was the first three-loop PWR in Taiwan constructed by Westinghouse. For the last few years, the TRACE model of Maanshan NPP was developed and several kinds of transients were performed. Recently, the RELAP5/MOD3.3 code is another important development priority for our group. In 2015, the RELAP5/MOD3.3 model of Maanshan NPP was developed with SNAP interface. To expand the applicability of Maanshan RELAP5/MOD3.3 model, the loss of flow transient was analyzed in this research. Hence, two analyses- Partial Loss of Flow (PLOF) and Complete Loss of Flow (CLOF) were performed in this research. From the analysis results, including power, core flow, pressurizer pressure and cladding average temperature, were similar to the results of TRACE model. It indicates that Maanshan RELAP5/MOD3.3 model can predict this transient well.