The Analysis and Study of ELAP Event and Mitigation Strategies Using TRACE Code for Maanshan PWR(NUREG/IA-0496)

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Publication Information

Manuscript Completed: January 2018
Date Published: February 2019

Prepared by:
Jung-Hua Yang, Jong-Rong Wang, Chunkuan Shih, Yu Chiang,
Chun-Fu Huang, Shao-Wen Chen, Ting-Yi Wang*, and 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

Kirk 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

Availability Notice


In this study, TRACE code was used to evaluate the postulated Extended Loss of AC Power (ELAP) accident in Maanshan nuclear power plant (NPP), determining whether RCS water level will drop down below Top of Active Fuel (TAF) while the 5th diesel generator and gas turbines are all disabled when the accident occurred. The scenario and assumptions of postulated ELAP event in this study were referred to the WCAP-17601-P report and NUREG-1953 report. To analyze the effectiveness of URG and FLEX strategies, this research will run a base case without any mitigation strategy and four cases with multiple mitigation strategy under different conditions. According to the results of simulation, it can be found that all four cases in this study can keep RCS water level above TAF, ensuring the safety function of reactor.

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