United States Nuclear Regulatory Commission - Protecting People and the Environment

RELAP5/MOD3.3 Model Assessment of Maanshan Nuclear Power Plant with SNAP Interface (NUREG/IA-0472)

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Publication Information

Manuscript Completed: March 2016
Date Published: October 2017

Prepared by:
Chunkuan Shih, Jong-Rong Wang, Shao-Wen Chen, Hao-Chun Chang, Show-Chyuan Chiang*, and 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

Prepared as part of:
The Agreement on Research Participation and Technical Exchange
Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

Published by:
Division of Systems Analysis
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Availability Notice


RELAP5 is a very important analysis tool for Taiwan Power Company and is still used for the transient analysis of the Taiwan NPPs. The version of RELAP5 for Taiwan Power Company is RELAP5/MOD3.3 and the input deck of RELAP5 is established by the ASCII files. Symbolic Nuclear Analysis Package (SNAP) is an interface of NPP analysis codes which developed by U.S. NRC and Applied Programming Technology, Inc. Different from the traditional input deck in ASCII files, the graphical control blocks and thermal hydraulic connections make researches comprehend the whole power plant and control system more easily. Additionally, for the last few years, the TRACE/SNAP model of Maanshan NPP was developed and several kinds of transient events were performed. Based on the past research experience and SNAP advantages, the RELAP5/MOD3.3 model of Maanshan NPP was developed with SNAP interface in this research. Maanshan NPP is located on the southern coast of Taiwan. Its nuclear steam supply system is a type of PWR designed and built by Westinghouse for Taiwan Power Company. A startup test data and two transient results were used to compare with the results of RELAP5/MOD3.3 model for the new-developed analysis model assessment. The predictions of RELAP5/MOD3.3 were consistent to the startup test and historical transient data results. It indicates that there is a respectable accuracy for the Maanshan NPP RELAP5/MOD3.3 model.

Page Last Reviewed/Updated Tuesday, November 07, 2017