Analysis of Main Steam Line Break Accident for 3-Loop PWR with RELAP5/MOD3.3 Code (NUREG/IA-0527)

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Publication Information

Manuscript Completed: February 2021
Date Published: August 2021

Prepared by:
Chunkuan Shih, Jong-Rong Wang, Chih-Chia Chiang, Yuh-Ming Ferng, Shao-Wen Chen, and Tzu-Yao Yu*

National Tsing Hua University and 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)

Availability Notice


In Taiwan, many prediction analysis for different purposes are investigated with different system codes, such as RELAP5 developed by US NRC. The main purpose of this study was to simulate Maanshan NPP PWR Main Steam Line break (MSLB) inside-containment by using RELAP5/MOD3.3, and then to discuss the results of this model by referring to Maanshan FSAR. Furthermore, sensitivity study of discharge coefficient is also included. In addition, the peak cladding temperature is maintaining under the criteria value in 10CFR50.46 and the results of this RELAP5/MOD3.3 model indicates reasonable thermal-hydraulic phenomena and presents good agreements with FSAR. The sensitivity analysis results show that the variations of break flow rate were governed by discharge coefficient. This study demonstrated that a methodology of RELAP5/MOD3.3 model for Maanshan PWR has been successfully developed, and the present simulation results and analysis can be used for safety analyses and further transient applications.

Page Last Reviewed/Updated Wednesday, September 01, 2021