期刊文献+

陶瓷球床在堆内辐照物理计算

下载PDF
导出
摘要 本文的主要内容是在中国先进研究堆(CARR)堆内固进行态氚增殖剂陶瓷球床辐照实验的物理计算。本文采用Monte Carlo粒子输运模拟程序MCNP5对陶瓷球床进行堆内建模计算得到不同功率下球床的中子注量率、发热功率和产氚速率。通过更改氚增殖剂球床组件的结构尺寸或堆功率来满足实验的要求,得到满足实验要求的球床结构,在堆内辐照陶瓷球床组件进行物理计算和分析,从而为热工计算分析提供数据,为整体装置在堆内辐照实验提供安全分析。最终得到球床的中子注量率为5.63x10^(12)n/cm^2s,球床的发热功率为491.9W。 The main content of this paper is in-pile irradiation experiment of International Thermonuclear Fusion Reactor Experiment(ITER)tritium breeder blanket module(TBM)have been carried out in China Advanced Research Reactor(CARR).This paper adopts the Monte Carlo particle transport MCNP5simulation program to modeling the pebble bed.By using the statistical pebble-bed neutron flux,counting card energy deposition and yield,get the pebble bed under different power of neutron flux rate,heating power and the tritium production rateis introduced into reactor.In order to ensure the safety of the reactor and ceramic pebble beds assembly,and to meet requirements of the experiment,it can be realized by changing the structure size of pebble beds or the power of reactor,in pile irradiation breeder pebble bed assembly physical calculation and analysis,so as to provide data for the thermodynamic calculation and analysis,the pile irradiation experiments provide safety analysis as a whole install.Finally the physics showed neutron flux of the pebble beds is5.63x1012n/cm2s,heating power is491.9W.
出处 《科技创新导报》 2017年第20期95-97,99,共4页 Science and Technology Innovation Herald
关键词 陶瓷球床组件 堆内辐照 物理计算和分析 Tritium breeder pebble beds assembly In-pile irradiation Physical calculation and Analysis
  • 相关文献

参考文献2

二级参考文献30

  • 1Boccaccini L V.Design descriptiondocument for the Rebut P H.ITER:the first experimental fusion reactor[J].FusionEngineering and Design,1995,27:3-6.
  • 2Aymar R.Status of ITER project[J].Fusion Engineering and Design,2002,61-62:5-12.
  • 3Vetter J E.Report from the re-established test blanket working group (TBWG) for theperiod of the ITER transitional arrangement (ITA)[R].2001.
  • 4Pan C H.Definition and development strategy of DEMO fusion reactor inChina[R].Presented at TBWG-12 meeting,ITER Naka Joint Working Site,2004.
  • 5Gaincarli L.Report from the re-established Test Blanketworking group (TBWG) for theperiod of the ITER Transitional Arrangement (ITA)[R].2005.
  • 6Abdou M.Suggested US Plans and Strategy for ITER Test Blanket[R].Presented at APEX/TBMMeeting,UCLA,2003.
  • 7Abramov V,Borisov A,Goroshkin,et al.Design description document for the Russianfederation ceramic helium cooled test blanket module,design description documentstatus:25.05.2001 version 2[R].Moscow:2001.
  • 8European Helium Cooled Pebble Bed (HCPB) test blanket modules[R].ITER FEAT Final DesignReport,Forschungszentrum Karlsruhe,June,2001.
  • 9Mikio Enoeda.Design description document for the Japanese helium-cooled solidbreeder,test blanket module[R].ITER FEAT Final Design Report,JAERI,April,2001.
  • 10Feng K M,Zhang G S,Wang X Y,et al.Design description document for the Chinesehelium-cooled Solid Breeder Test Blanket Module (CH HC-SB) TBM (intermedialreport)[R].SWIP,2004.

共引文献52

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