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反应堆动态参数的蒙特卡罗计算研究 被引量:4

Calculation of Reactor Kinetic Parameters with Monte Carlo Method
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摘要 介绍缓发中子有效份额(βeff)、有效中子代时间(Λeff)和本征值的概念及其蒙特卡罗程序计算方法。采用Prompt Method方法计算得到βeff;微扰法得到Λeff;采用瞬发中子密度衰减直接拟合法和间接求解法得到本征值;将各种反应性状态下的拟合得到临界c本征值,并与实验测量的c值进行比对,结果符合很好;并对动态参数蒙特卡罗程序计算的各种方法进行不确定度分析。 Basic conceptions of kinetic parameters,including effective delayed neutron fraction(),effective neutron generation time() and α eigenvalue,and Monte Carlo calculation methods for these values are systematically introduced in this paper.is obtained with a "Prompt Method".Perturbation method is chosen to obtain.And then α eigenvalue is obtained by two ways,(i) prompt neutron density attenuation,in other words "direct simulation of time evolvement",(ii) indirect method using the result of kp and neutron generation time.Linear fitting is used to get the critical αc eigenvalues which match well with experimental ones.And uncertainties of kinetic parameters with different methods using Monte Carlo method are also analyzed.
出处 《核动力工程》 EI CAS CSCD 北大核心 2012年第2期116-122,共7页 Nuclear Power Engineering
基金 中国工程物理研究院科学技术发展基金(2009A0103002) 国家自然科学基金(10775081)
关键词 动态参数 蒙特卡罗模拟 PROMPT Method 微扰 时间模拟 Kinetic parameters Monte Carlo method Prompt method Perturbation Time evolvement
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参考文献11

  • 1Kiedrowski Brian,Brown Forrest,Wilson Paul.Calcu-lating Kinetics Parameters And Reactivity Changes WithContinuous-Energy Monte Carlo[C].Physor 2010-Advances in Reactor Physics to Power the NuclearRenaissance,Pittsburgh,Pennsylvania,USA,2010.
  • 2Tonoike Kotaro,Miyoshi Yoshinori,Kikuchi Tsukasa,etal.Kinetic Parameterβeff&frasll Measurementon Low Enriched Uranyl Nitrate Solution with SingleUnit Cores(600&phi,280T,800φ)of STACY[J].Journal of Nuclear Science and Technology,2002,39(11):1227-1236.
  • 3杨鑫.次临界装置动态参数计算与测量[D].北京:清华大学工程物理系学士学位论文,2009.
  • 4Bretscher M M.Evaluation of Reactor Kinetic Para-meters without the Need for Perturbation Codes[C].International Meeting on Reduced Enrichment forResearch and Test Reactors,Jackson Hole,WyomingUSA,1997.
  • 5Spriggs Gregory D,Busch Robert D,Campbell Joann M.Calculation of the Delayed Neutron Effectiveness Factorusing Ratios of k-Eigenvalues[J].Annals of NuclearEnergy,2001,28(5):477-487.
  • 6Meulekamp Robin Klein,Marck Steven C,Van der.Calculating the Effective Delayed Neutron Fraction withMonte Carlo[J].Nuclear Science and Engineering,2006,152:142-148.
  • 7Verboomen B,Haeck W,Baeten P.Monte CarloCalculation of the Effective Neutron Generation Time[J].Annals of Nuclear Energy,2006,33(10):911-916.
  • 8杜金峰,贺仁辅,刘汉刚.深次临界装置α本征值计算方法比较研究[J].原子能科学技术,2004,38(3):231-234. 被引量:3
  • 9邱有恒,邓力.次临界α本征值计算中的时间选取方法[J].核科学与工程,2007,27(2):182-186. 被引量:4
  • 10LI Zeguang,YANG Xin,LI Tianya,et al.Monte CarloSimulations and Experimental Validations ofαEigen-values[C].PHYSOR 2010-Advances in ReactorPhysics to Power the Nuclear Renaissance,Pittsburgh,Penn-sylvania,USA,2010.

二级参考文献9

  • 1贝尔GI 格拉斯登S 千里译.核反应堆理论[M].北京:原子能出版社,1979.25-32.
  • 2杜书华 等.输运问题的计算机模拟[M].长沙:湖南科学技术出版社,1989.138-152.
  • 3Hansen GE,Roach WH.Six and Sixteen Group Cross Sections for Fast and Intermediate Critical Assemblies: LAMS-2543[R].US: Los Alamos National Laboratory,1961.
  • 4Perel RL,Wagschal JJ.Direct and Indirect Computation of the Transport Equation Eigenvalues [J].NuclSciEng,1986,94:409~412.
  • 5杜书华.输运问题的计算机模拟[M].长沙:湖南科学技术出版社,1988,262-265.
  • 6Brockway D,et al.Monte Carlo a Calculation[R].LaUR-85-1224,1985.
  • 7Parsons D K.Alphalike Calculations with MCNP[J],Trans Am Nucl Soc,2001.84.
  • 8John F Zino,Tom Williamson,et al.Technical Report -Subcritical Measurements Research Program for Fresh and Spent Material Test Reactor Fuels[R].WSRC-MS-99-00370,1999.
  • 9Briesmeiter J F,et al.MCNP-A General Monte Carlo N particle transport code,version[R].LA-13709-M,2000

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