期刊文献+

溶液堆物理计算程序FMCAHR燃耗功能及其验证

Burn-up Function of Fuel Management Code for Aqueous Homogeneous Reactors and Its Validation
下载PDF
导出
摘要 介绍了FMCAHR程序的燃耗计算模型及流程,并使用燃耗基准题和DRAGON程序对燃耗计算结果进行验证。验证结果表明,FMCAHR燃耗计算功能的准确性较高,适用于溶液堆的燃耗计算分析。 Fuel Management Code for Aqueous Homogeneous Reactors(FMCAHR) is developed based on the Monte Carlo transport method,to analyze the physics characteristics of aqueous homogeneous reactors.FMCAHR has the ability of doing resonance treatment,searching for critical rod heights,thermal hydraulic parameters calculation,radiolytic-gas bubbles' calculation and burn-up calculation.This paper introduces the theory model and scheme of its burn-up function,and then compares its calculation results with benchmarks and with DRAGON's burn-up results,which confirms its burn-up computing precision and its applicability in the burn-up calculation and analysis for aqueous solution reactors.
出处 《核动力工程》 EI CAS CSCD 北大核心 2011年第4期127-130,142,共5页 Nuclear Power Engineering
关键词 溶液堆 燃耗计算 FMCAHR DRAGON Solution reactors Burn-up calculation FMCAHR DRAGON
  • 相关文献

参考文献4

  • 1International Atomic Energy Agency.Homogeneous Aqueous Solution Nuclear Reactors for the Production of Mo-99 and Other Short Lived Radioisotopes[R].IAEATECDOC-1601,2008.
  • 2Leszczynski F,Lopez Aldama D,Trkov A.WIMS-D Li-brary Update-Final Report of a Coordinated Research Project[R].2006.
  • 3汪量子,姚栋,王侃.溶液堆物理计算程序FMCAHR开发[J].核动力工程,2011,32(2):1-5. 被引量:2
  • 4Argonne Naional Laboratory.Argonne Code Center:Benchmark Problem Book[M].ANL-7416 Supplement 2,1977.

二级参考文献6

  • 1International Atomic Energy Agency, Homogeneous Aqueous Solution Nuclear Reactors for the Production of Mo-99 and other Short Lived Radioisotopes[C]. Consul- Tants Meeting, VIENNA, June 2007, Austria, IAEA, 2008, 1-4.
  • 2Yoshinori Miyoshi, Yoshinori Miyoshi, Tsukasa Ikuchi, Kinetic Parameter βcff/I Measurement on Low Enriched Uranyl Nitrate Solution with Single Unit Cores (600 Ф, 280T, 800 Ф) of STACY[J]. Journal of Nuclear Science and Technology, 2002, 39(11): 1227-1236.
  • 3Deng Li, Xie-Zhongsheng, Zhang Jianming. MCMG: A 3-D Multigroup P3 Monte Carlo Code and Its Bench- marks[J]. Journal of Nuclear Science and Technology, 2000, 37(7): 608-614.
  • 4Francisco J, Souto, Robert H, et al. Analysis of the Effects of Radiolytic-Gas Bubbles on the Operation of Solution Reactors for the Production of Medical Isotopes [J]. Nuclear Science and Engineering, 2005, 150(1): 322-335.
  • 5Souto F J, Heger A S. A Model to Estimate Volume Change due to Radiolytic Gas Bubbles and Thermal Ex pansion in Solution Reactors[R]. LA-UR-01-0673, 2001.
  • 6Chuvilin D Yu, Khvostionov V E, Markovskij D V. Production of 89Sr in Solution Reactor[J]. Applied Radiation and Isotopes, 2007, 65: 1087-1094.

共引文献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