The development of Lungmen ABWR TRACE safety analysis model
One of the main R & D work in nuclear engineering is the development of computer programs related to nuclear power plant (NPP) safety analysis.The advanced thermal hydraulic code named TRACE for NPP safety analysis is developing by U.S.NRC now.Lungmen NPP is the first ABWR NPP in Taiwan and still under construction.The safety analysis of NPP is very important work.In general,the description and results of the safety analysis for the transients are in the Final Safety Analysis Report (FSAR) of NPP.In this research,the development of the Lungmen NPP TRACE model for the safety analysis is performed.The transient analysis prediction of the TRACE model for Lungrmen NPP is also performed.The loss of feedwater flow (LOFW) transient data and MSIV (Main Steamline Isolation Valve) closure direct scram transient data from FSAR are used to compare with the predicted results of the Lungmen NPP TRACE model.The compared results indicate that there are the similar trends of parameters between the TRACE model of Lungmen NPP and FSAR for the analysis of the LOFW transient and MSIV closure direct scram (MSIVCD)transient.
TRACE ABWR Lungmen safety analysis
Hao-Tzu Lin Jong-Rong Wang Chunkuan Shih
Institute of Nuclear Energy Research, Atomic Energy Council, R.O.C., 1000, Wenhua Rd.,Chiaan Village Institute of Nuclear Engineering and Science, National Tsing Hua University, 101 Section 2,Kuang Fu
国际会议
台湾
英文
4461-4465
2011-12-11（万方平台首次上网日期，不代表论文的发表时间）