使用自主开发的一维输运/燃耗/可视化计算程序系统VisualBUS1.0和HENDL1.1/MG数据库, 对233U, 235U和239Pu的热溶液临界球基准实验和237Np, 241Am和244Cm的金属快裂变临界球问题进行校核.和国际上广泛使用的各种程序和数据库的模拟计算结果以及相关实验结果进行综合对比和分析, 初步验证了HENDL1.1/MG中裂变核素核数据的可靠性和应用性, 同时也进一步证明了VisualBUS1.0程序的正确性.
参考文献
[1] | Lemmel H D,et al.The NJOY Nuclear Data Processing System,Version 91.LA-12740-M,Los Alamos National Laboratory,1994. |
[2] | 许德政,吴宜灿,高纯静等.核科学与工程,2005,24:366. |
[3] | MacFarlane R E.TRANSX 2:A Code for Interfacing MATXS Cross-section Libraries to Nuclear Transport Codes.LA-12312-MS,1993. |
[4] | International Handbook of Evaluated Criticality Safety Benchmark Experiments.Organization for Economic Cooperation and Development,Nuclear Energy Agency,NEA /NSC/DOC(95)03/I-VII,September 2003 Edition. |
[5] | Briesmeister J F ed.MCNP4C General Monte Carlo N-Particle Transport Code.Los Alamos National Laboratory,LA-13709-M,2000. |
[6] | Alcouffe R E,Baker R S,Brinkley F W,et al.DANTSYS:A Diffusion Accelerated Neutral Particle Transport Code System.Los Alamos National Laboratory,LA-12969-M,June 1995. |
[7] | Gwin R,Magnuson D W.Critical Experiments for Reactor Physics Studies.ORNL 60-4-12,Oak Ridge National Laboratory,September,1960. |
[8] | Gwin R,Magnuson D W.Nucl Sci and Eng,1962,12:364. |
[9] | Kruesi F E,Erkman J O.Lanning D D.Critical Mass Studies of Plutonium Solutions.HW-24514,General Electric Company,Richland,Washington,19 May,1952. |
[10] | Fox L J K,Gilley L W,Gwin R,et al.Critical Parameters of Uranium Solutions in Simple Geometry.Neutron Physics Annual Report,ORNL-2609,42,Oak Ridge National Laboratory,1958. |
[11] | Fox J K,Gilley L W,Gwin R,et al.Critical Parameters of 235U and 233U Solutions in Simple Geometry,Neutron Physics Annual Progress Report.ORNL-2842,76,Oak Ridge National Laboratory,1959. |
[12] | Hemanth DIAS,Nigel TANCOCK,Angela CLAYTON,Critical Mass Calculations for 241Am,242Am and 243Am.The 7th International Conference on Nuclear Criticality Safety,ICNC2003. |
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