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MCMG蒙特卡罗多群-连续截面耦合中子输运计算 被引量:4

Coupled Neutron Transport Calculation of MCMG Monte Carlo Multigroup-Continuous Cross Section
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摘要 本文针对多群蒙特卡罗计算省时但共振自屏处理存在缺陷,以及连续截面蒙特卡罗输运计算精度高但计算费时的问题,发展了一种多群-连续截面耦合计算方法。该方法在自主研发的三维中子-光子耦合输运蒙特卡罗程序MCMG中得到应用,通过多个模型的计算验证了方法的有效性。MCMG耦合计算取得了与连续点截面MCNP程序一致的结果,其计算速度较MCNP的提高了1倍左右。 It is well known that the computation time of multigroup Monte Carlo calculation is much less than that of the continuous(point-wise) calculation.However,there are some difficulties in the multigroup treatment about resonance and self-shielding.Although the good precision of point-wise cross section transport calculation can be obtained,the consumed time is too long.A coupled calculation of the multigroup and the point-wise cross section was developed in self-development 3D neutron and photon transport Monte Carlo code MCMG.The validity of this method was proved by testing of many models.The almost same results with the point-wise cross section MCNP code were achieved.The coupled calculation of MCMG is about one time faster than that of MCNP.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2013年第3期329-333,共5页 Atomic Energy Science and Technology
基金 中国工程物理研究院基金资助项目(2011A0103006 2012A0102005) 国家磁约束核聚变能研究专项资助(2010GB111001)
关键词 蒙特卡罗 共振自屏 多群-连续截面耦合计算 MCMG MCNP Monte Carlo resonance and self-shielding coupled calculation of multigroup and point-wise MCMG MCNP
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参考文献7

  • 1MATSUMOTO H, OUISLOUMEN M, TAKE- DA T, et al. Development of spatially dependent resonance shielding method[J]. Journal of Nucle- ar Sciences and Technology, 2005, 42(8): 688- 694.
  • 2HEBERT A, MARLEAU G. Generalization of the Stamm' ler method for the self-shielding of resonant isotopes in arbitrary geometries[J]. Nu- clear Science and Engineering, 1991, 108(3):230-239.
  • 3HEBERT A. Development of the subgroup pro- jection method for resonance self-shielding calcu lation [J]. Nuclear Science and Engineering, 2009, 162(1): 56-75.
  • 4邓力,胡泽华,李刚,李树.三维多群P_5中子输运蒙特卡罗程序MCMG及检验[J].原子能科学技术,2011,45(8):943-948. 被引量:13
  • 5邓力,胡泽华,陈朝斌,李刚.三维多群中子输运蒙特卡罗程序MCMG-Ⅱ基准检验[J].原子能科学技术,2009,43(B12):32-36. 被引量:9
  • 6CHADWICK M B, OBLOZINSKY P, HER- MAN M, et al. ENDF/B-VII. 0: Next generation evaluated nuclear data library for nuclear science and technology[J]. Nuclear Data Sheets, 2006, 107:2 931-3 060.
  • 7ROUSSIN R W. BUGLE-80 couple 47 neutron, 20 gamma-ray, P3 cross section library for LWR shielding calculations, DLC-75[R]. USA: ORNL, 1980.

二级参考文献23

  • 1蒋校丰,栾兴峰,邓力.多群蒙特卡罗程序MCMG的开发与基准校验[J].核动力工程,2007,28(1):9-12. 被引量:6
  • 2DENG Li, XIE Zhongsheng, ZHANG Jianming. MCMG : A 3 D multigroup Monte-Carlo code and its benchmarks[J]. J Nucl Sci Tech, 2000, 37 (7) : 608-614.
  • 3DENG Li, XIE Zhongsheng, LI Shu. Multi group Monte-Carlo transport and burnup calculation[J]. Ann Nucl Energy, 2003, 27(10): 936-942.
  • 4BRIESMEISTER J F. MCNP-A general Monte-Carlo code for N-particle transport code, LA-12625-M[R]. USA: LANL, 1997.
  • 5EMMETT M B. MORSE-CGA, a Monte-Carlo radiation transport code with array geometry capability, ORNL-6174[R]. USA: ORNL, 1985.
  • 6ROUSSIN R W. BUGLE-80 couple 47 neutron, 20 gamma-ray, P3 cross section library for LWR shielding calculations, DLC-75[R]. USA: ORNL, 1980.
  • 7CHADWICK M B, OBLOZINSKY P, HERMAN M, et al. ENDF/B-Ⅶ. 0: Next generation evaluated nuclear data library for nuclear science and technology[J]. Nuclear Data Sheets, 2006, 107 : 2 931-3 060.
  • 8PETRIE L M, LANDERS N F, KENO V A. An improved Monte-Carlo criticality program with supergrouping, NUREG/CR-0200[R]. USA: ORNL, 1983.
  • 9ENGLE W W, Jr. A one-dimensional discrete ordinates transports code with anisotropic scattering]R]. USA: ORNL, 1997.
  • 10RHOADES W A, MYNATT F R. The DOT-Ⅳ: Two dimensional discrete ordinates transport code[R]. USA: ORNL, 1973.

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