期刊文献+

加速器驱动的次临界系统的燃耗分析计算和堆芯优化设计 被引量:5

Calculation and Analysis of Burnup and Optimum Core Design in Accelerator Driven Sub-critical System
下载PDF
导出
摘要 以加速器驱动的次临界系统(ADS)在事故情况下仍处于次临界、keff随燃耗时间变化的最大范围不超过1.5%和包壳材料HT9钢可承受的最大辐照损伤的前提下,将堆芯燃料区分为嬗变区和增殖区,并将整个过程保持嬗变区的燃料成分不变。通过对ADS燃料的组成成分、堆芯布置和堆芯功率分布等方面的研究,在Pu的外层富集度与内层富集度之比为1.0~1.5范围内,调整增殖区的燃料成分,并利用MCNP和ORIGEN耦合的COUPLED2程序计算keff随燃耗时间的变化。同时,综合考虑功率展平、次锕系核素的嬗变率和燃耗深度等因素,建立1套符合工程实际的次临界系统。 The premise of the accelerator driven sub-critical system(ADS) in the accident is still subcritical,the biggest keff change with burn time is less than 1.5% and the cladding material,HT9 steel,can withstand the maximum radiation damage,core fuel area is divided into fuel transmutation area and fuel multiplication area,and fuel transmutation area maintains the same fuel composition in the whole process.Through the analysis of the composition of the fuel,shape of core layout and the power distribution,etc.,supposed outer and inner Pu enrichment ratio range of 1.0-1.5,then the fuel components of fuel multiplication area was adjusted.Time evolution of keff was calculated by COUPLED2 which coupled with MCNP and ORIGEN.At the same time the power peaking factors,minoractinides transmutation rate desired to maximization and burnup were considered.A sub-critical system fitting for engineering practice was established.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2011年第6期700-704,共5页 Atomic Energy Science and Technology
基金 清华大学自主科研项目资助(20091081263)
关键词 KEFF 嬗变 燃耗 keff transmutation burnup
  • 相关文献

参考文献4

  • 1Accelerator-driven system (ADS) and fast reac- tors (FR) in advanced nuclear fuel cycles: A comparative studyER3. France: OECD, 2002.
  • 2黄锦华,阳彦鑫.工业用铅冷加速器驱动次临界系统(ADS)初步概念设计[J].核科学与工程,2006,26(4):343-352. 被引量:2
  • 3SELTBORG P. External source effects and neu tronics in accelerator-driven systems[D]. Stock holm, Sweden: Department of Nuclear and Reac tor Physics Royal Institute of Technology, 2003.
  • 4COMETTO M, NAB C, WYDLER P. OECD/ NEA Benchmark Calculations for Accelerator Driven Systems Sixth Information Exchange Meeting on Actinide and Fission Product Parti tioning and Transmutation[C]. Madrid, Spain: Es. n. 1, 2001: 168-169.

二级参考文献6

  • 1Peter Wydler,Baetsle L H.Closing the Nuclear Fuel Cycle:Issues and Perspectives[C].// Proc.5th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation.Paris:OECD Nuclear Energy Agency,1999:31-49.
  • 2阳彦鑫.二维输运燃耗程序BURN2D使用说明[R].成都:核工业西南物理研究院,2004.
  • 3Kaguo Fuuta,et al.BISON 1.5[R].Tennessee:Oak Ridge National Labolatory,1987.
  • 4O'Dell R D,et al.A Code Package for Two-Dimensional,Diffusion-Accelerated,Neutral-Particle Transport[R].Tennessee:Oak Ridge National Laboratory,1986.
  • 5Hill R N,et al.Physics Studies of Weapons Plutonium Disposition in the IFR Closed Fuel Cycles[J].Nuclear Science and Engineering,1995,121:17-31.
  • 6Park W S,et al.A Preliminary Design Concept of the HYPER System[J].Korean Nuclear Society,2002,34(1):42-59.

共引文献1

同被引文献19

  • 1PARK W S, SONG T Y, LEE B O, et al. A preliminary design concept of the HYPER system [J]. Korean Nuclear Society, 2002, 34: 42-59.
  • 2SELTBORG P E R. External source effects and neutronics in accelerator-driven systems [D]. Stockholm, Sweden: Department of Nuclear and Reactor Physics Royal Institute of Technology, 2003.
  • 3COMETTO M, NA B C, WYDLER P. OECD/ NEA benchmark calculations for accelerator driven systems [C]// Sixth Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation. Madrid, Spain: [ s. n.], 2001: 168-169.
  • 4徐铼,李泽华.快堆物理基础[M].北京:中国原子能出版传媒有限公司,2011:67.
  • 5韩嵩.COUPLE2使用手册[M].北京:清华大学核能与新能源技术研究院,2006.
  • 6TAKN I, NEITZEL H J, CHEN H Y, et al. Thermal hydraulic analysis of window target unit for LBE cooled XADS[R]. Karlsruhe.. Fors- chungszentrum Karlsruhe, 2004.
  • 7JOHN D B, NOZOMU F, JAMES W, et al. Evaluation of the start-up core physics tests at Japan's high temperature engineering test reactor (annular core loadings)[M]. USA: Argonne National Laboratory, 2010.
  • 8吴总鑫,张作义.先进核能系统和高温气冷堆[M].北京:清华大学出版社,2004:18.
  • 9熊鑫.加速器驱动的次临界反应堆物理方案研究[D].北京:清华大学核能与新能源技术研究院,2012.
  • 10徐铢,李泽华.快堆物理基础[M].北京:中国原子能出版传媒有限公司,2011:67.

引证文献5

二级引证文献7

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