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新概念熔盐堆物理计算方法研究及程序设计 被引量：8

Nuclear Calculation and Program Development for Molten Salt Reactor
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摘要 考虑新概念熔盐堆燃料盐的流动特性,从基本的粒子守恒方程出发,推导了熔盐堆的中子动力学模型,并采用数值方法对3种工况下熔盐堆的临界问题进行计算,考察流动对有效增殖系数、快中子分布、热中子分布及缓发中子先驱核分布的影响。结果表明:质量流量对有效增殖系数的影响很小,对热中子分布的影响比对快中子分布的影响大,而质量流量越大,缓发中子先驱核移出堆芯的比率也越大。 Considering the fuel salt flow effect of the molten salt reactor, the neutron dynamic model was derived based on the particle conservation equations, and the critical problem was calculated by numerical method under three working conditions to study the flow effect to effective multiplication factor, fast neutron, thermal neutron and delayed neutron precursors distribution. The calculated results show that the influence of mass flow on the effective multiplication factor is very small, and the influence on the thermal neutron distribution is larger than that on the fast neutron distribution. In addition, the percentage of the delayed neutron precursors moving out the core increases with the increasing mass flow.
作者 张大林 秋穗正 刘长亮 苏光辉 贾斗南
机构地区 西安交通大学动力工程多相流国家重点实验室 西安交通大学核能科学与技术学院
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2008年第12期1103-1108,共6页 Atomic Energy Science and Technology
基金 国家自然科学基金资助项目(10575079)
关键词 熔盐堆 中子动力学模型 中子扩散 缓发中子先驱核 流动效应 数值计算 molten salt reactor neutron dynamic model neutron diffusion delayed neutron precursors flow effect numerical calculation
分类号 TL426 [核科学技术—核技术及应用] TL325 [核科学技术—核技术及应用]
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参考文献7

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同被引文献42

  • 1陶文铨.数值传热学[M].西安：西安交通大学出版社,1989..
  • 2Rosenthal M,Kasten P,Briggs R. Molten salt reac-tors--History,status,potential[J]. Nuclear Applica- tions and Technology, 1971), 8 (2) : 107-117.
  • 3James A L. The fourth generation of nuclear power [J]. Progress in Nuclear Energy, 2002, 40 (3/4): 301-307.
  • 4David Le Blanc. Molten s.alt reactors:A new begin- ning for an old idea[J].Nuclear Engineer and De- sign,2010,240(6) : 1644-1656.
  • 5Ignatiev V. MOSART fuels and container materials study:Case for Na, Li,Be/F solvent system [C]// Proceedings of the 2003 ANS/ENS International Winter Meeting (GLOBAL 2003). USA: Hyatt Re- gency, 2003.
  • 6Nuttin A, Heuer D. Potential of thorium molten salt reactors:Detailed calculations and concept evolution with a view to large scale energy production [J]. Progress in Nuclear Energy, 2005,46 (1) : 77-79.
  • 7Delpeeh S, Merle-Lucotte E, Heuer D. Reactor physics and reprocessing scheme for innovative molten salt reactor systena[J]. Journal of Fluoring Chemistry, 2009,130(1) : 11-17.
  • 8Merle-Lucotte E, Mathieu L, Heuer D. Influence of the processing and salt composition on the thorium molten salt reactor[J]. Nuclear Technology, 2008, 163(3) : 358-365.
  • 9Mathieu L, Heuer D, Brissot R. The thorium molten salt reactor.. Moving oil from the MSBR [J]. Progress in Nuclear Energy,2006,48(7) :664-679.
  • 10Briant R C, Weinberg A M. Molten fluorides as power reactor fuels[J]. Nuclear Science and Engineering, 1957, 2: 797-803.

引证文献8

二级引证文献9

原子能科学技术
2008年 第12期

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