研究生: |
張敏娟 |
---|---|
論文名稱: |
TRITON/GenPMAXS/PARCS/TRACE計算平台應用於沸水式反應器爐心計算 BWR Core Neutronic Simulations using TRITON/GenPMAXS/PARCS/TRACE Sequence |
指導教授: | 許榮鈞 |
口試委員: |
薛燕婉
施純寬 |
學位類別: |
碩士 Master |
系所名稱: |
原子科學院 - 核子工程與科學研究所 Nuclear Engineering and Science |
論文出版年: | 2014 |
畢業學年度: | 102 |
語文別: | 中文 |
論文頁數: | 100 |
中文關鍵詞: | 輕水式反應器 、晶格計算 、爐心計算 、中子與熱水流耦合計算 |
外文關鍵詞: | light water reactor, lattice calculations, core calculations, neutronics & thermal-hydraulics coupling |
相關次數: | 點閱:2 下載:0 |
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TRITON/GenPAMXS/PARCS/TRACE (TGPT),為一結合多種程式的爐心計算平台,適用各式反應器的爐心計算。TRITON中的控制序列T-DEPL為二維的晶格計算程式,透過決定論法處理中子遷移方程式和燃耗計算,自動產生問題相依的截面; GenPMAXS作為介面程式,目標將各種晶格計算程式產生的截面轉檔成PARCS能接受的PMAXS檔案;而多維的爐心模擬程式PARCS主要求解中子擴散方程式,亦能耦合熱水流程式TRACE進行迭代計算,精準地分析爐心的狀況。本論文首先利用TRITON模擬BWR燃料晶格,並進行一系列的參數靈敏度的探討,並根據此經驗應用於ABWR的爐心分析,以商業化的認證程式CASMO4/CMSLink/SIMULATE3 (CMS)的結果作為參考,客觀分析TGPT的優勢與劣勢,以建立一套可信的爐心計算平台。
比較TGPT和CMS的計算結果得其觀察和結論:針對BWR燃料組件問題,TRITON計算隨燃耗變化的kinf和CASMO-4的結果十分吻合,對此條件下產生的截面有信心後,再交由PARCS/TRACE進行爐心計算,在此發現耦合TRACE的必要性,因為BWR爐心緩和劑密度變化太大,PARCS精簡的熱水流模型不足以正確模擬爐心狀態。對於本研究分析的龍門電廠ABWR簡化爐心,PARCS/TRACE不論使用CASMO-4或TRITON截面和SIMULATE-3在keff的差異皆小於300 pcm,若使用相同的CASMO-4截面,無論徑向的功率變化或軸向各項參數的變化,如功率、熱中子通率、緩和劑密度和燃料溫度,PARCS/TRACE和SIMULATE-3皆有一致的趨勢,其中些許的不同可能來自於程式差異;若PARCS/TRACE使用TRITON產生的截面,即為TGPT的計算結果,和SIMULATE-3結果就有較大的差距,在徑向功率上約有25%的差異,因為除了程式差異外,又再加入截面不同造成的影響,更詳細的差異來源有待進一步的探討。
[1]Yamamoto, Akio, and Tomohiro Endo. "Overview of core simulation methodologies for light water reactor analysis." (2011).
[2]DeHart, Mark D., et al. "Assessment of TRITON and PARCS for full-core MOX fuel calculations." American Nuclear Society 2005 Annual Meeting. (2005).
[3]DeHart, Mark D., and Stephen M. Bowman. "Reactor physics methods and analysis capabilities in SCALE." Nuclear Technology 174.INL/JOU-11-22946 (2011).
[4]Wang, Dean, Brian J. Ade, and Andrew Ward. "Cross Section Generation Guidelines for TRACE-PARCS. " No. ORNL/TM-2012/518. Oak Ridge National Laboratory (ORNL), (2013).
[5]Xu, Yunlin, et al. "Application of TRACE/PARCS to BWR stability analysis."Annals of Nuclear Energy 36.3 (2009): 317-323.
[6]Stålek, Mathias, and Christophe Demazière. "Development and validation of a cross-section interface for PARCS." Annals of Nuclear Energy 35.12 (2008): 2397-2409.
[7]陳淑娟. "TRACE 程式之中子動力模式研究與應用." 清華大學核子工程與科學研究所學位論文 (2010): 1-102.
[8]張佳穎. "龍門電廠 TRACE/PARCS 模式建立與應用." 清華大學核子工程與科學研究所學位論文 (2012): 1-108.
[9]何愛玲. "龍門電廠主蒸汽閥門關閉之預期暫態未急停分析." 清華大學核子工程與科學研究所學位論文 (2013): 1-120.
[10]Edenius, Malte, et al. "CASMO-4, A Fuel Assembly Burnup Program, User’s Manual." Studsvik0SOA-9501, Studsvik of America, Inc (1995).
[11]Smith, Kord S., and Joel D. Rhodes III. "Full-core, 2-D, LWR core calculations with CASMO-4E." Proc. Int. Conf. PHYSOR. (2002).
[12]DeHart, Mark D. "Advancements in generalized-geometry discrete ordinates transport for lattice physics calculations." A154. pdf in Proc. Of PHYSOR-2006(2006): 10-14.
[13]Umbarger, Jerry A., and A. S. DiGiovine. "SIMULATE-3, Advanced Three-Dimensional Two-Group Reactor Analysis Code, User’s Manual." Studsvik/SOA-92/01 (1992).
[14]陳健湘., “燃料晶格計算程式CASMO-4理論介紹.”, (2003).
[15]童武雄., "爐心燃料設計審查講義. ",(2009).
[16]ORNL., "SCALE: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design. " ORNL/TM-2005/39, Version 6.1. Oak Ridge National
Laboratory, Oak Ridge, TN, USA. (2011)
[17]Xu, Y., and T. Downar. "GenPMAXS code for generating the PARCS cross section interface file PMAXS." Purdue University, School of Nuclear Engineering, West Lafayette, IN, USA (2012).
[18]Downar, T., et al. "PARCS v3.0 US NRC Core Neutronics Simulator User Manual." University of Michigan(2012).
[19]Yunlin Xu, D.B., "TRACE-PARCS-Coupling.", in TRACE User Workshop, P.T.U.S.N.R.C. SIMULATOR, Editor (2011).
[20]Yamamoto, Akio, et al. “Benchmark problem suite for reactor physics study of LWR next generation fuels.” Journal of Nuclear Science and Technology 39.8 (2002): 900-912.
[21]Yamamoto, Akio. "Generalized coarse-mesh rebalance method for acceleration of neutron transport calculations." Nuclear science and engineering 151.3 (2005): 274-282.
[22]LWR Next Generation Fuels Benchmark(2004); Available from: http://rpg.jaea.go.jp/else/rpd/report/report1/LWR-benchmark/index.htm.
[23]Ade, B. J., "SCALE/TRITON Primer: A Primer for Light Water Reactor Lattice Physics Calculations. " ORNL/TM-2011/21, Oak Ridge National Laboratory, Oak Ridge, TN(2012).
[24]Company, T.P., "Final Safety Analysis Report:LUNGMEN NUCLEAR POWER STATION UNITS 1&2."(2007).
[25]台電龍門核電廠訓練教材_v6.
[26]Ade, B.J., "Generation of Collapsed Cross Section for HATCH 1 Cycles 1-3 and Generation of Generic BWR Reflector Cross Sections. " ORNL/LTR-2012/559, Oak Ridge National Laboratory, Oak Ridge, TN(2012).