United States Nuclear Regulatory Commission - Protecting People and the Environment

Main Steam Line Break Analysis for Lungmen ABWR (NUREG/IA-0476)

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Publication Information

Manuscript Completed: February 2016
Date Published: November 2016

Prepared by:
Chunkuan Shih, Jong-Rong Wang, Ai-Ling Ho, 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:
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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Abstract

The object of this paper is to develop methodologies for analyzing the behaviors of fuel rod, vessel, and containment during main steamline break (MSLB) transient. The broken area of the RPV side was assumed to be 0.0984m2 (flow limiter). And the broken area of the main steam header side was assumed to 0.319m2 (main steam line area). According to FSAR, for conservative assumption, MSIVs started to close at 0.5sec and fully closed at 5.0sec after the transient started. The results of TRACE/PARCS coupling calculation were compared with those of both FSAR and GOTHIC data, indicating that the TRACE/PARCS coupling model has the ability to predict the MSLB transient, and both RPV integrity and containment integrity criteria are met. After that, the output data from TRACE/PARCS calculation was put into FRAPTRAN code as boundary conditions to analyze the thermo-mechanical behavior and calculate the stress, strain, oxide thickness, etc. The values of these factors were compared with the criteria. And the final results show that the fuel rod integrity criteria are met.

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