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临界计算程序KENO的开发与应用 被引量:1

DEVELOPMENT AND APPLICARTION OF CRITICAL CALCULATION CODE KENO
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摘要 KENO程序是美国橡树岭国家实验室研制的一个大型蒙特卡罗临界计算程序,该程序的几何能力较强,可描述任意复杂的三维几何结构问题,还具有较强的截面能力,可使用HansenRoach16群截面库,也可使用AMPX工作格式截面库。KENOVa还具有大群处理的特点,节省机器内存。程序给出的主要计算量是K_(eff)。文章介绍KENO程序的主要特征、开发、改进、微机化以及推广应用的情况。 KENO is a large code of Monter Carlo critical calculation,compiled by Oak Ridge Nationallaboratory of U. S.A. and widely used in the world.It is improved all the time from the first ap-pearing at 1969. Now it is up to KENO Ⅳ, KENO Va. They have great capacity of geometry,can be used in any problems of complex 3-dimension geometric figure,meanwhile,they can usecross section library of Hansen Roach 16 groups or AMPX type with their better ability of crosssection. In addition,KENO Va has the characteristic in deal with large groups,can save compu-ter RAM. The program gives K_(eff) as the main calculation. The paper introduces the major fea-tures of KENO program,its improvement,development,micrcacomputerization and popularizedapplication.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 1995年第1期1-8,共8页 Atomic Energy Science and Technology
关键词 KENO 临界计算 几何能力 截面能力 蒙特卡罗法 KENO critical calculation Geometry capacity Section ability Large groups Personal computer
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参考文献5

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同被引文献12

  • 1李金鸿,张松柏,E.F.Kryuchkov,G.V.Tikhomirov.用于燃耗计算的三维MCCOOR程序系统[J].核动力工程,2006,27(3):16-19. 被引量:7
  • 2CHANG G S. MCOW:Liking MCNP and ORIGEN2 for fuel burnup analysis [ R ]. USA:Idaho National Engineer- ing and Environmental Laboratory,2005.
  • 3Moore R L,Schnitzler B G,Wemple C A,et al. MOCUP: MCNP-ORIGEN2 Coupled Utility Program [ R ]. USA:I-daho National Engineering Laboratory, 1995.
  • 4Trellue H R, Poston D I. User's Manual, Version 2.0 for MONTEBURNS, Version 5 B [ R ]. USA : Los Alamos Na- tional Laboratory, 1999.
  • 5SHE Ding,XU Qi,WANG Kan. RMC1.0-Development of Monte Carlo Code for Reactor Analysis[ R]. 18th Interna- tional Conference on Nuclear Engineering (ICONE18), Xi'an, China :2010.
  • 6DeHart M D. TRITON : A Two-Dimensional transport and Depletion Module for characterization of spent nuclearFuel [ R ]. USA : Oak Ridge National laboratory,2006.
  • 7Petrie L M, Landers N F, Hollenbach D F, et al. KENO V. a:An improved Monte Carlo Criticality Program [ R ]. USA : Oak Ridge National Laboratory ,2006.
  • 8Gauld I C, Hermann O W, Wesffall R M. ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Ac- tinide Transmutation, Fission Product buildup and De- cay, and Associated Radiation Source Terms [ R ]. USA: Oak Ridge National Laboratory,2006.
  • 9Weaver K D, Zhao X, Pilat E E, et al. A PWR Thorium Pin Cell Bumup Benchmark [ R ]. USA : Idaho National Engineering and Environmental Laboratory,2000.
  • 10师学明,张本爱.输运与燃耗耦合程序MCORGS的开发[J].核动力工程,2010,31(3):1-4. 被引量:13

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