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CFD方法在压水堆安全分析中的应用现状和发展趋势

Status and development trend of CFD method used in pressure water reactor safety analysis
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摘要 为更好地利用CFD方法解决压水堆安全分析问题,简要介绍CFD方法,着重阐述其在硼稀释、混合和热分层以及受压热冲击等压水堆安全分析问题的应用现状,并提出CFD与系统程序的耦合计算、流固耦合计算和CFD与中子动力学程序的耦合计算将是CFD方法在该领域的发展重点. To make better use of CFD method in pressure water reactor safety analysis,the CFD method is introduced briefly and its application in boron dilution,mixing and thermal stratification,and pressurized thermal shock in pressure water reactor safety is especially detailed.The techniques such as CFD and system program coupling calculation,fluid-structure coupling calculation and CFD and neutron dynamics program coupling calculation should be the development focus of the CFD method application in nuclear reactor safety analysis.
出处 《计算机辅助工程》 2013年第3期57-62,70,共7页 Computer Aided Engineering
关键词 CFD方法 压水堆 安全分析 硼稀释 混合和热分层 受压热冲击 CFD method pressure water reactor safety analysis boron dilution mixing and thermal stratification pressurized thermal shock
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参考文献28

  • 1HOHNE T, KLIEM S, ROHDE U, et al. Boron dilution transients during natural circulation flow in PWR: experiments and CFD simulations[ C]//14th Int Confer Nucl Energy(ICONE-14) , 2007, 238(8) : 1987-1995.
  • 2KLIEM, S, StiHNEL T, ROHDE. U, et al. Experiments at the mixing test facility ROCOM for benchmarking of CFD codes[J. Nucl Eng & Des, 2007, 238(3): 566-576.
  • 3MORETTI F, MELIDEO D, DELNEVO A, et al. CFD analysis of a slug mixing experiment conducted on a VVER-1000 modelE J ]. Sci & Technol Nuel Installations, 2009(2009) : 436218-436229.
  • 4HERTLEIN R J, UMMINGER K, KLIEM S, et al. Experimental and numerical investigation of boron dilution transients in pressure water reactors[J]. Nucl Technol, 2003, 141 ( 1 ) : 88-107.
  • 5GAVRILAS M, KIGER K. ISP-43: rapid boron dilution transient experiment[ R]. OECD Nuclear Energy Agency, 2001.
  • 6PRASSER H M, GRUNWALD G, HOHNE T, et al. Coolant mixing in a pressure water reactor: deboration transients, steam-line breaks, anti emergency core cooling injection[ J]. Nucl Technol, 2003, 143 (1) : 37-56.
  • 7ROHDE U, HOHNE T, KLIEM S, et al. Fluid mixing and flow distribution in a primary circuit of a nuclear pressure water reactor : validation of CFD codes[ J]. Nuel Eng & Des, 2007, 237(15-17) : 1639-1655.
  • 8周欣,朱丽兵.非均匀硼稀释瞬态三维流场计算[J].核技术,2010,33(2):124-126. 被引量:3
  • 9WESTIN J. Boundary conditions and list of available data for CFD-validation [ R]. Report Memo U07-26, Vattenfall R&D AB, Alvkarleby, Sweden, 2007 : 1-17.
  • 10ZBORAY R, MANERA A, NICENO B, et al. Investigations on mixing phenomena in single-phase flows in a T-junction geometry[ C ]//12th Int Topical Meeting Nucl Reactor Therm Hydraulics( NURETH-12), Sheraton Station Square, Pittsburgh, Pennsylvania, 2007.

二级参考文献25

  • 1陈炳德.CFD技术在国外燃料组件热工水力性能及格架研制中的应用[J].国外核动力,2004,25(2):1-6. 被引量:4
  • 2张毅雄,杨宇.稳压器波动管热分层分析[J].核动力工程,2006,27(6):13-17. 被引量:14
  • 3桂学文,骆邦其,蔡琦.RELAP5程序与三维时空中子动力学模型的耦合以及改进研究[J].核动力工程,2007,28(1):49-52. 被引量:5
  • 4卢东华.安注时反应堆压力容器下降环腔内流动与传热实验研究:[博士学位论文].西安:西安交通大学能源与动力工程学院,2001..
  • 5Yu Y J, Park S H, Sohn G H. Structural Evaluation of Thermal Stratification for PWR Surge Line[J]. Nuclear Engineering and Design, 1997, 178: 211-220.
  • 6US NRC.NRC Bulletin 88-08, Thermal Stresses in Piping Connected to Reactor Coolant Systems[S]. 1988.
  • 7US NRC. NRC Bulletin 88-11, Pressurizer Surge Line Thermal Stratification[S]. 1988.
  • 8Ensel C, Colas A, Barthez M. Stress Analysis of a 900MW Pressurizer Surge Line Including Stratification Effects[J]. Nuclear Engineering and Design, 1995, 153: 197-203.
  • 9(德)海恩慈·赫尔威格.传热词汇A-Z,基本概念与详尽诠释[M].彭晓峰,张扬译.北京:机械工业出版社,2007.
  • 10AEA Technology plc. CFX10.0: Additional Variables. ANSYS Europe Ltd. 2005.

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