The Development and Application of TRACE/PARCS Model for Lungmen ABWR (NUREG/IA-0434)

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Publication Information

Manuscript Completed: April 2013
Date Published: December 2013

Prepared by:
Jong-Rong Wang, Chia-Ying Chang*, 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

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

TRACE code developed by US NRC is an advanced thermal hydraulic system code for nuclear power plant safety analysis. The feature of 3-D reactor vessel simulation in TRACE allows complex flow modeling and this kind of vessel is employed in Lungmen TRACE model. PARCS is a multi-dimensional neutronic simulator which is able to incorporate a 3-D reactor core with one-to-one fuel assembly simulation for the realistic representative. The state-of-the-art is that PARCS is capable of being coupled to TRACE, which provides the temperature and flow field information to PARCS during calculations. In this research, the TRACE/PARCS model of Lungmen nuclear power plant is established first. Then, the TRACE/PARCS model is used for two transient analyses - 3 RIPs trip and HPCF inadvertent startup. These events could test the ability of the coupling of TRACE and PARCS. Moreover, SNAP, a user-friendly interface developed by the US NRC and APT, provides users a graphical working environment and enables to animate the simulation as an alternative presentation of calculation results.