United States Nuclear Regulatory Commission - Protecting People and the Environment

Performing Uncertainty Analysis of IIST Facility SBLOCA by TRACE and DAKOTA (NUREG/IA-0428)

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Publication Information

Manuscript Completed: March 2013
Date Published: September 2013

Prepared by:
Jong-Rong Wang, Chiung-Wen Tsai*, Hao-Tzu Lin, Chunkuan Shih*

Institute of Nuclear Energy Research, Atomic Energy Council, R.O.C.
1000, Wenhua Rd., Chiaan Village, Lungtan, Taoyuan, 325, TAIWAN

*Institute of Nuclear Engineering and Science, National Tsing Hua University,
101 Section 2, Kuang Fu Rd., Hsinchu, TAIWAN

K. Tien, NRC Project Manager

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

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Abstract

Nowadays, the increasing computing speed realizes the quantification of propagation of input uncertainties to output data with Monte Carlo simulation or modified simulation methods. The best estimate plus uncertainty (BEPU) methods have been proposed to be used instead of typical conservative methodologies. Based on the CAMP activity, this project demonstrates the capability of SNAP-TRACE-DAKOTA for 2 % small break LOCA (SBLOCA) of IIST experiment. The number of samples was determined by Wilks’ formula to generate the upper bound of peak cladding temperature (PCT) with 95/95 confidence level and probability. The PCTs by IIST experiment and best-estimate calculation are 804 K and 861 K respectively. The mean value and standard deviation of the 59 trial by SNAP-TRACE-DAKOTA are 938.7 K and 63.6 K respectively, and the maximum value of PCT is 1054 K.

Page Last Reviewed/Updated Wednesday, December 11, 2013