期刊文献+

等效均匀化方法在连续能量蒙特卡罗均匀化群常数上的应用 被引量:1

Application of Equivalence Methods on Monte Carlo Method Based Homogenization Multi-group Constants
在线阅读 下载PDF
导出
摘要 连续能量蒙特卡罗方法均匀化群常数直接用于堆芯均匀计算,不能与非均匀计算保持反应率和界面流守恒,需进一步处理使其满足等效均匀化原理。本工作研究广义均匀化理论(GET)和超级均匀化方法(SPH)在蒙特卡罗均匀化中的应用,并数值验证简化压水堆堆芯和C5G7基准题。研究表明,GET和SPH的应用提高了蒙特卡罗均匀化群常数堆芯扩散计算的精度,可作为蒙特卡罗等效均匀化方法。 The multi-group constants generated via continuous energy Monte Carlo method do not satisfy the equivalence between reference calculation and diffusion calculation applied in reactor core analysis.To the satisfaction of the equivalence theory,general equivalence theory(GET) and superhomogenization method(SPH) were applied to the Monte Carlo method based group constants,and a simplified reactor core and C5G7 benchmark were examined with the Monte Carlo constants.The results show that the calculating precision of group constants is improved,and GET and SPH are good candidates for the equivalence treatment of Monte Carlo homogenization.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2013年第3期343-349,共7页 Atomic Energy Science and Technology
基金 国家自然科学基金资助项目(11175168)
关键词 均匀化 等效 蒙特卡罗方法 广义均匀化理论 超级均匀化方法 homogenization equivalence Monte Carlo method general equivalence theory superhomogenization method
作者简介 李满仓(1984-),男,黑龙江海伦人,工程师,博士,反应堆物理专业
  • 相关文献

参考文献23

  • 1BROWN F B, MARTIN W R, MOSTELLER R D. Monte Carlo--Advances and challenges[C] // Workshop at PHYSOR-2008. Interlaken, Switz- erland: [s. n. ], 2008.
  • 2MARTIN B. Advances in Monte Carlo methods for global reactor analysis[C]//Joint Internation- al Topical Meeting on Mathematics & Computa- tion and Supercomputing in Nuclear Applications (M&C+ SNA 2007). California, USA: [s. n. ], 2007.
  • 3ILAS G, RAHNEMA F. A Monte Carlo based nodal diffusion model for criticality analysis of spent fuel storage lattiees[J]. Annals of Nuclear Energy, 2003, 30(10): 1 089-1 108.
  • 4van der MARCK S C, KUIJPER J C, OPPE J. Homogenized group cross section by Monte Carlo [C]// PHYSOR-2006 American Nuclear Society's Topical Meeting on Reactor Physics. Vancouver BC, Canada: [s. n.], 2006.
  • 5TOHJOH M, WATANABE M, YAMAMOTO A. Application of continuous-energy Monte Carlo code as a cross-section generator of BWR core calculations [J]. Annals of Nuclear Energy, 2005, 32(8): 857-875.
  • 6REDMOND E L. Multigroup cross section gen- eration via Monte Carlo methods [D]. USA: Massachusetts Institute of Technology Depart- ment of Nuclear Engineering, 1997.
  • 7RAHNEMA F, ILAS G, HUDSON N H, et al. On the few-group cross-section generation meth- odology for PBR analysis[J]. Annals of Nuclear Energy, 2006, 33(11-12): 1 058-1 070.
  • 8BLOMQUIST R N. VIM Monte Carlo neutron/ photon transport code[EB/OL]. [2010]. http: ///www. vim. anl. gov.
  • 9MAIOROV L V. MCU code: MCU proiect home page [EB/OL]. [2010]. http: // www. mcu. vver. kiae. ru/eareal.
  • 10LEPPANEN J. PSG2/Serpent: A Monte Carlo reactor physics burnup calculation code [EB/ OL]. [2010]. http://www, naontecarlo, vtt. fi.

同被引文献1

引证文献1

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部