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固态钍基熔盐堆堆芯物理参数计算 被引量:2

Calculation of Core Physics Parameter of Thorium Molten Salt Reactor with Solid Fuel
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摘要 针对中国科学院设计的2 MW固态钍基熔盐堆(TMSR-SF)堆芯,采用蒙特卡罗程序MCNP精确描述堆芯TRISO包覆燃料颗粒、燃料球排布,建立了包含燃料元件、熔盐冷却剂、石墨反射层、中心石墨通道、控制棒及反射层通道的三维全堆芯模型,计算了TMSR-SF初始有效增殖因数、中子能谱、功率分布、控制系统价值、停堆裕量、反应性系数、中子动力学参数等堆芯物理参数,为TMSR-SF的物理优化及热工安全分析提供必要的参数。 Chinese Academy of Sciences has developed the 2 MW core design of thorium molten salt reactor with solid fuel (TMSR-SF). By using the core design as a reference case, the Monte Carlo MCNP code was used to develop an accurate description of the arrangement of TRISO fuel particles and fuel pebbles. A three-dimensional model was developed for the whole core including all the fuel elements, coolant, graphite reflector, central graphite channels, control rods and channels in the reflector. The following reactor core physics parameters were calculated for TMSR-SF: Primary effective multi- plication factor, neutron energy spectrum, power distribution, control system worth, shutdown margin, reactivity coefficient and neutron kinetic parameters. The results provide reactor core physics parameters for physical optimization and thermal hydraulic steady and transient analysis for TMSR-SF.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2015年第B05期126-131,共6页 Atomic Energy Science and Technology
基金 国家自然科学基金资助项目(91326201) 国家自然科学基金青年项目资助(11105103) 国家国际科技合作专项资助(2012DFG61030)
关键词 固态钍基熔盐堆 MCNP 堆芯物理参数 thorium molten salt reactor with solid fuel MCNP core physics parameter
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  • 1INGERSOLL D, FORSBERG C. Overview andstatus of the advanced high-temperature reactor[C]// Proceedings of the International Congresson Advanced Nuclear Power Plants. Reno, Ne-vada: [s. n. ],2006.
  • 2江绵恒,徐洪杰,戴志敏.未来先进核裂变能——TMSR核能系统[J].中国科学院院刊,2012,27(3):366-374. 被引量:201
  • 3XIAO Y,HU L, FORSBERG C,et al. Licen-sing considerations of a fluoride salt cooled hightemperature test reactor[C] // 21st InternationalConference on Nuclear Engineering. Chengdu:[s. n. ],2013.
  • 4FORSBERG C W,HU L, PETERSON P F, etal. Fluoride-salt-cooled high-temperature reactors(FHRs) for power and process heat[R]. Cam-bridge :MIT Center for Advanced Nuclear Ener-gy Systems, 2012.
  • 5FRATONI M. Development and applications ofmethodologies for the neutronic design of thepebble bed advanced high temperature reactor(PB-AHTR)[D]. Berkeley: University of Cali-fornia, 2009.
  • 6柴晓明,王侃,余纲林.温度相关核截面数据库在MCNP计算中的必要性研究[J].原子核物理评论,2006,23(2):111-114. 被引量:7
  • 7BRETSCHER M M. Evaluation of reactor kinet-ic parameters without the need for perturbationcodes[C] // International Meeting on Reduced En-richment for Research and Test Reactors. Jack-son Hole: [s. n. ],1997.
  • 8WILLIAMS D, TOTH L,CLARNO K. Assess-ment of candidate molten salt coolants for the ad-vanced high temperature reactor (AHTR) [M].United States: Department of Energy,2006.

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