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          NRC Library  Document Collections  NUREG-Series Publications  Publications Resulting from International AgreementsThe Analysis and Study of ELAP Event and Mitigation Strategies Using TRACE Code for Maanshan PWR(NUREG/IA-0496)

On this page: Publication Information AbstractDownload complete document NUREG/IA-0496 (PDF – 1.17 MB)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 Abstract 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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