本論文之主要目的就是在SNAP介面下修改先前建立的龍門電廠PARCS模式，並與龍門電廠TRACE模式結合，以提供熱水流程式TRACE較先進的三維爐心計算，而TRACE模式內建的功率計算方式為：時間功率表和點中子動力。這種熱水流程式結合中子動力計算程式的計算方法可以做為「最佳估計」的方法；此外，透過此種計算方式可以觀察到電廠系統熱水流反應與爐心現象相互影響的結果。
龍門電廠TRACE/PARCS模式於本論文中將進行三個案例分析：終期安全分析報告第15章之三個爐內泵跳脫事故、進步型反應器特有的選擇性插棒機制、以及控制棒擾動造成的同相與異相不穩定性分析。三個爐內泵跳脫事故中的功率由TRACE的三種功率計算方法分別執行運算，並相互比較，分析結果皆與終期安全分析報告趨勢大致相同。選擇性插棒機制係使用PARCS模式特有的控制棒移動的功能來模擬控制棒插入，來降低爐心功率；其結果在不同的初始條件下有著相似的趨勢，也符合起動測試所述的規範：功率減少40%至60%。控制棒擾動亦是由PARCS模式來設定控制棒的移動，依控制棒的移動是否相同，分成同相與異相擾動，由模擬的結果可明顯的觀察到功率以及燃料組件內流率的震盪。
目前龍門電廠100%額定功率、100%額定流率之TRACE/PARCS模式已建立完成，並運用在數種案例分析上，待龍門電廠商業運轉後即可進行程式的驗證與比對；除此之外，對國內其他三座核電廠的PARCS模式建立將會有一定的幫助。

The objectives of this thesis are to establish Lungmen PARCS model with SNAP interface, and to couple the thermal-hydraulic code TRACE for more advanced calculations in 3D core. This TH/NK calculation is believed to be a “best-estimate” calculation where the local interactions between the nuclear power plant and the core phenomena could be observed easily.
In this research, three cases were analyzed using Lungmen TRACE/PARCS model: 3 RIP trip in FSAR, the SCRRI function, and the instability due to control rod perturbation. To analyze the 3 RIP trip, three power generations implemented in TRACE were used respectively, which are power table, point kinetic, and coupled to PARCS. The results from three different power generations are in good agreements with FSAR results. The SCRRI mechanism was performed under several initial conditions and different RIP runback settings, and the power reductions were found to meet the criteria as specified in the startup test procedures. The two instability modes, core-wide and out-of phase, were modeled by control rod perturbations; oscillations of reactor power and fuel assembly inlet flow can be observed.
In conclusion, Lungmen TRACE/PARCS model has been completed and can be used for safety analysis. After the commercial operation of Lungmen power plant, this coupled code would be verified. In addition, the experiences of completing Lungmen PARCS model can promote the establishments of the PARCS models of other three nuclear power plants.

[1] J. Freixa, and A. Manera, “Analysis of an RPV upper head SBLOCA at the ROSA facility using TRACE”, Nuclear Engineering and Design, vol. 240, pp. 1779–1788, 2010
[2] K. Ivanov, M. Avramova, “Challenges in coupled thermal–hydraulics and neutronics simulations for LWR safety analysis”, Annals of Nuclear Energy, vol. 34, pp. 501-513, 2007
[3] T. Kozlowski, R. Matthew Miller, and T. J. Downar, “Consistent Comparison of the Codes RELAP5 PARCS and TRAC-M PARCS for the OECD MSLB Coupled Code Benchmark”, Nuclear Technology, vol. 146, pp. 15-28, 2004
[4] D. Lee, T. J. Downar, and A. Ulses, “Analysis of the OECD/NRC BWR Turbine Trip Transient Benchmark with the Coupled Thermal-Hydraulics and Neutronics Code TRAC-M/PARCS”, Nuclear Science and Engineering, vol. 148, pp. 291–305, 1998
[5] A. Bousbia-Salah , J. Vedovi, F. D’Auria, K. Ivanov, and G. Galassi “Analysis of the Peach Bottom Turbine Trip 2 Experiment by Coupled RELAP5-PARCS Three-Dimensional Codes” , Nuclear Science and Engineering, vol. 148, pp. 337–353, 2004
[6] March-Leuba, J., Pere, R.B. and Cacuci, D.G., “Calculation of Limit Cycle Amplitudes in Commercial Boiling Water Reactors”, Transactions of the American Nuclear Society, vol. 46, 1984
[7] Y. Xu, T. J. Downar, R. Walls, K. Ivanov, J. Staudenmeier, J. March-Lueba, “Application of TRACE/PARCS to BWR stability analysis”, Annals of Nuclear Energy, vol. 36, pp. 317–323, 2009
[8] T. Kozlowski, T. J. Downar, Y. Xu, A. Wysocki, K. Ivanov, J. Magedanz, M. Hardgrove, J. March-Leuba, N. Hudson, and D. Woodyatt, “TRACE/PARCS Analysis of the OECD/NEA Oskarshamn-2 BWR Stability Benchmark”, PHYSOR-2012, Knoxville, Tennessee, USA, 2012
[9] J. R. Wang, H. T. Lin, W. C. Wang, S. M. Yang, and C. Shih, “TRACE Models and Verifications for LUNGMEN ABWR”, ANS Winter Meeting, Washington D.C., USA, 2009
[10] J. R. Wang, H. T. Lin, Y. H. Cheng, W. C. Wang, and C. Shih, “TRACE modeling and its verification using Maanshan PWR start-up tests”, Annals of Nuclear Energy, vol. 36, pp. 527–536, 2009
[11] J. H. Yang, J. R. Wang, H. T. Lin, and C. Shih, “LBLOCA analysis for the Maanshan PWR nuclear power plant using TRACE”, Energy Procedia, vol. 14, pp. 292-297, 2012
[12] Y. H. Cheng, J. R. Wang, H. T. Lin, and C. Shih, “Benchmark calculations of pressurizer model for Maanshan nuclear power plant using TRACE code”, Nuclear Engineering and Design, vol. 239, pp. 2343–2348, 2009
[13] 陳淑娟，「TRACE程式之中子動力模式研究與應用」，國立清華大學核子工程與科學研究所，碩士論文，中華民國九十九年
[14] C. Y. Chang, H. T. Lin and J. R. Wang, and C. Shih, “TRACE/PARCS Modelling of RIPs Trip Transients for Lungmen ABWR”, PHYSOR-2012, Knoxville, Tennessee, USA, 2012
[15] C. Y. Chang, H. T. Lin, J. R. Wang, and C. Shih, “Studies on SCRRI Performances in ABWR with TRACE/PARCS”, TopSafe-2012, Helsinki, Finland, 2012
[16] T. S. Feng, J. R. Wang, H. T. Lin, and C. Shih “TRACE/PARCS Modelling of Feedwater Pump Trip Transients for Lungmen ABWR”, ICONE20-POWER2012, Anaheim, California, USA, 2012
[17] J. R. Wang, H. T. Lin, W. C. Wang, and C. Shih, “Application of TRACE/PARCS/LAPUR to Lungmen ABWR stability analysis”, Transactions of the American Nuclear Society, vol. 105, Washington D.C., 2011
[18] Y. Xu, and T. J. Downar, GenPMAXS Code for Generating the PARCS Cross Section Interface File PMAXS, University of Michigan, 2009
[19] TRACE V5.0 USER’S MANUAL, Volume 2: Modeling Guidelines, U. S. Nuclear Regulatory Commission.
[20] Studsvik of America, Inc., and Studsvik Core Analysis AB, Copyright 1995, CASMO-4 使用手冊
[21] T. Downar, Y. Xu, V. Seker, and N. Hudson, PARCS v3.0 U.S. NRC Core Neutronics Simulator USER MANUAL, University of Michigan, 2010
[22] 李亮瑩，「龍門電廠RELAP5-RT控制系統輸入模式建立與暫態分析」，國立清華大學工程與系統科學系，碩士論文，中華民國九十七年
[23] 龍門電廠訓練教材_V6
[24] 核能研究所，龍門電廠SIMULATE-3爐心布局檔案，2009
[25] 核能研究所，龍門電廠CASMO-4晶格計算輸出檔，2009
[26] Studsvik of America, Inc., Copyright 1995, SIMULATE-3 使用手冊
[27] Taiwan Power Company, Final Safety Analysis Report: LUNGMEN NUCLEAR POWER STATION UNITS 1&2, 2007
[28] General Electric Company, Startup Test Prediction – Transient Test Prediction, 2005
[29] S. Maa, C. Shih, and Y. Yuann , “Integrated control system responses during load rejection transient for Lungmen ABWR Plant”, Annals of Nuclear Energy, vol. 38, pp. 1458–1472, 2011
[30] J. March-Leuba, and C. Thurston, “BWR Stability Methodology”, CAMP Meeting, Philadelphia, PA, USA, 2011