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气冷快堆燃料组件均匀化初步研究 被引量:3

Homogenization of Fuel Assembly of Gas-Cooled Fast Reactor
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摘要 气冷快堆是第4代核能系统候选方案之一,具有高温多用途、能增殖等优点。本工作以一气冷快堆的设计方案为研究对象,针对单组件模型和全堆芯模型,采用MCNP耦合ORIGEN的方法,计算了有关临界、燃耗过程的几个重要物理特性,比较了采用精细化结构和组件均匀化方法在计算精度、计算时间等的差别,说明了采用组件均匀化方法进行气冷快堆全堆燃耗计算的必要性和可行性。 Gas-cooled fast reactor (GFR) is one of generation 1V candidate reactor systems, featured with versatile usage because of high temperature, and economy because of fuel breeding. For a reference GFR core design, the criticality and burnup characteristics for the single assembly model and full core model were calculated through the coupling of MCNP and ORIGEN, and the differences in the calculation precision and calculation time were compared between the fine structure model and homogenized assembly model, respectively. As a result, the necessity and feasibility to adopt the homogenized assembly method in the GFR whole core burnup calculation were explained and discussed.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2009年第7期626-629,共4页 Atomic Energy Science and Technology
基金 国家自然科学基金资助项目(10675071)
关键词 气冷快堆 组件均匀化 燃耗 gas-cooled fast reactor assembly homogenization burnup
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参考文献5

  • 1DOE U S. Nuclear energy research advisory committee and the generation Ⅳ international forum: A technology roadmap for generation Ⅳ nuclear energy systems, GIF-002-00 [R]. [S. l.]: [s.n.], 2002.
  • 2HEJZLAR P, POPE M J, DRISCOLL M J, et al. Gas cooled fast reactor for generation IV service [R]. IS. l.]: Massachusetts Institute of Technology, 2004.
  • 3Idaho National Laboratory. Gas-cooled fast reactor (GFR) FY05 annual report[R]. USA: Idaho National Laboratory, 2005.
  • 4BRIESMEISTER J F. MCNP^TM-A general Monte Carlo N-particle transport code version 4C, LA13709M[R]. USA: LANL, 2000.
  • 5Oak Ridge National Laboratory. ORIGEN 2. 1. Isotope generation and depletion code-matrix exponential method, CCC-371 [ R ]. USA.. ORNL, 1996.

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