The Development of Lungmen ABWR TRACE Safety Analysis Model

Abstract:

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 Lungmen 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.

• Periodical: Applied Mechanics and Materials (Volumes 121-126)
• Pages: 4461-4465
• DOI: https://doi.org/10.4028/www.scientific.net/AMM.121-126.4461
• Online since: October 2011
• Authors: Hao Tzu Lin, Jong Rong Wang, Chun Kuan Shih
• Keywords: ABWR, Lungmen, Safety Analysis, Trace

References

[1] NRC: TRACE V5. 0 User's Manual, Office of Nuclear Regulatory Research (2010).

[2] Taiwan Power Company: Final Safety Analysis Report for Lungmen Nuclear Power Station Units 1&2 (FSAR) (2007).

[3] L.S. Kao, J.R. Wang, R.Y. Yuann, W.H. Tung, J.A. Jing, C.T. Lin: Parallel calculations and verifications of limiting transient analyses for Lungmen nuclear power plant. INER report, INER-A1609R, Institute of Nuclear Energy Research Atomic Energy Council, R.O.C. (2008).

[4] L.S. Kao, J.R. Wang, J.R. Tang, J.A. Jing, W.H. Tung, R.Y. Yuann, C.T. Lin, H.T. Lin: Development of Lungmen ABWR Thermal hydraulic Safety analysis Method-The Summary Report. INER report, INER-A1742R, Institute of Nuclear Energy Research Atomic Energy Council, R.O.C. (2008).

00.

00 2 Feedwater Flow drops thoroughly.

[5] 00.

[5] 00 3 The water level of reactor vessel descends to L3 lower level setting point, and it results in the reactor vessel scram and trip signals of four RIPs which were not connected to the M/G set.

[7] 53.

[10] 60 4 The water level of reactor vessel descends to L2 lower level setting point, and it causes the other six RIPs to trip.

[18] 28.

[15] 95 Table 2 The MSIVCD sequences of FSAR and TRACE. [2] Action Time (sec) FSAR TRACE 1 Closure of all main steamline isolation valves (MSIVs).

00.

00 2 MSIVs position scram initiated.

98.

98 3 Four RIPs trip initiated due to high reactor pressure.

[3] 10.

[3] 00 4 Safety/relief valves open due to high pressure.

[3] 68.

[3] 42 5 Safety/relief valves close.

[8] 76.

[7] 87 Fig. 1. The TRACE model of Lungmen NPP. Fig. 2. The comparison of NRWL between FSAR and TRACE for LOFW transient. [2] Fig. 3. The comparison of total reactivity between FSAR and TRACE for LOFW transient. [2] Fig. 4. The comparison of total reactivity between FSAR and TRACE for MSIVCD transient. [2] Fig. 5. The comparison of dome pressure between FSAR and TRACE for MSIVCD transient. [2].

DOI: 10.17816/brmma50037-38962