Using TRACE, MELCOR, CFD, and FRAPTRAN to Establish the Analysis Methodology for Chinshan Nuclear Power Plant Spent Fuel Pool (NUREG/IA-0482)

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Publication Information

Manuscript Completed: April 2017
Date Published: October 2018

Prepared by:
Jong-Rong Wang, Chunkuan Shih, Shao-Wen Chen, Yung-Shin Tseng, Yu Chiang, Wan-Yun Li, Jung-Hua Yang, Hsiung-Chih Chen, Show-Chyuan Chiang*, Tzu-Yao Yu*

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

Chinshan nuclear power plant (NPP) is the first plant in Taiwan and is a BWR/4 plant. People have more concern for the NPPs safety in Taiwan after Fukushima NPP disaster happened. Hence, we established the analysis methodology and performed the safety analysis of Chinshan NPP SFP (spent fuel pool) by using TRACE, MELCOR, CFD, and FRAPTRAN codes. There were two steps in this study. The first step was the establishment of Chinshan NPP SFP models by using TRACE, MELCOR, and CFD. Then, under the SFP cooling system failure condition (Fukushima-like accident), the transient analysis was performed. Additionally, the sensitive study of the time point for water spray was also performed. The next step was the analysis of the fuel rod performance by using FRAPTRAN and TRACE analysis results. Finally, the animation model of Chinshan NPP SFP was presented by using the SNAP animation function with MELCOR's results.