TRACE/SNAP Model Establishment of Chinshan Nuclear Power Plant for Ultimate Response Guideline (NUREG/IA-0478)

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Publication Information

Manuscript Completed: February 2016
Date Published: May 2017

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

*Institute of Nuclear Engineering and Science, National Tsing Hua University; Nuclear and New Energy Education and Research Foundation
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

In this research, the TRACE/SNAP model of Chinshan BWR/4 nuclear power plant (NPP) was established for the simulation and analysis of ultimate response guideline (URG). The main actions of URG are the depressurization and low pressure water injection of the reactor and containment venting. This research focuses to assess the URG utility of Chinshan NPP under Fukushima-like conditions. This study consists of three steps. The first step is the establishment of Chinshan NPP TRACE/SNAP model. In order to evaluate the system response of TRACE/SNAP model, startup tests and FSAR data were used to compare with the results of TRACE. The second step is the URG simulation and analysis under Fukushima-like conditions by using Chinshan NPP TRACE/SNAP model. In this step, the no URG case was also performed in order to evaluate the URG effectiveness of Chinshan NPP. In addition, the sensitivity study of URG and the required raw water injection were also performed. According to TRACE analysis results, the URG can keep the peak cladding temperature (PCT) below the criteria 1088.7 K under Fukushima-like conditions. It indicates that Chinshan NPP can be controlled in a safe situation. If Chinshan NPP does not perform the URG under Fukushima-like conditions, the water level may drop lower than TAF (top of active fuel) which means a safety issue about the fuel rods may be generated. In order to confirm the mechanical property and integrity of fuel rods, the final step is the analysis of FRAPTRAN.