期刊文献+

大功率压水堆堆芯燃料管理设计 被引量:8

In-Core Fuel Management Design of Large Power PWR
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摘要 设计了一种大功率压水堆堆芯,对其中可燃毒物装载方案、平衡循环布置、首循环装料及过渡循环方案进行了研究。采用特征统计算法CSA燃料管理优化程序,快速高效地搜索堆芯装载和可燃毒物配置优化方案。采用堆芯核设计程序CPACT进行全堆计算,结果真实可靠。分别设计了18个月和24个月换料两种方案,计算结果表明,在满足堆芯燃料管理所有限值要求的前提下,两种方案均从第4循环开始进入平衡循环。 A large power PWR core was designed. The burnable absorber reloading, the equilibrium cycle core design, reloading of the first and transition cycles were studied. The fuel management optimization code based on characteristic statistic algorithm (CSA) was used for global search efficiently. The core physics analysis code CPACT was used for core calculation. The cycle lengths of 18 months and 24 months were designed separately. The result shows that for each design, the basic design constraints are all satisfied and the equilibrium is reached quickly at the fourth cycle.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2012年第B09期397-402,共6页 Atomic Energy Science and Technology
关键词 燃料管理 循环长度 CSA CPACT fuel management cycle length CSA CPACT
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参考文献5

  • 1郑明光,叶成,韩旭.新能源中的核电发展[J].核技术,2010,33(2):81-86. 被引量:42
  • 2HU Yongming, LIU Zhihong, SHI Xiuan. De-velopment and verification of quick and precise core physics analysis code[C]//PHYSOR 2010- International Conference on the Physics of Reac- tors. Pittsburgh ANS, 2010.
  • 3石秀安,刘志宏,胡永明.含有可燃毒物的压水堆核电站堆芯装料设计优化研究[J].核科学与工程,2008,28(2):138-146. 被引量:3
  • 4刘志宏,胡永明,石秀安.秦山二期核电站多循环换料设计优化研究[C]//第十二届反应堆数值计算与粒子输运学术会议.合肥:[出版者不详],2008.
  • 5赵晶,刘志宏,胡永明.含IFBA可燃毒物组件物理特性研究[C]//第十三届反应堆数值计算与粒子输运学术会议.西安.[出版者不详],2010.

二级参考文献21

  • 1苑春强.美国的新能源政策[J].国际资料信息,2001(12):6-9. 被引量:2
  • 2刘勇 康立山 等.非数值并行算法--遗传算法[M].北京:科学出版社,1998..
  • 3康立山.非数值并行算法--模拟退火算法[M].北京:科学出版社,1998..
  • 4Kim Y J, Downar T J, Sesonske A. Optimization of Core Reload Design for Low leakage Fuel Management in Pressurized Water Reactor. Nuclear Science and Engineering [J], 1987, 96, 85-101.
  • 5Suh J S, et al. Optimized Automatic Reload Program for Pressurized Water Reactors Using Simple Direct Optimization Techniques. Nuclear Science and Engineering[J], 1990, 105:371-382.
  • 6Akio Yammoto. A Quantitative Comparison of Loading Pattern Optimization Methods for In-Core Fuel Management of PWR [J]. Journal of Nuclear Science and Technology, 1997, 34(4):339-347.
  • 7Dechaine M D, Feltus M A. Nuclear Fuel Management Optimization Using Genetic Algotithms[J]. Nucl Tech, 1995, 111:109-114.
  • 8Adem E, Melih G. A . PWR reload optimization code (XCore) using artificial neural networks and genetic algorithms[J]. Ann. Nucl Energy, 2003, 30:35-53.
  • 9Johansen B J. ALPS: An Advanced Interactive Fuel Management Package. Proc. of Topl. Mtg[C]. on Advances in Reactor phys. Vol. Ⅲ, 324, Knoxville, TN,April 11, 1994.
  • 10Haling R K. Operating strategy for maintaining optimum power distribution throughout life. TID-7672, USAEC, 1964.

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