期刊文献+
任意字段
题名或关键词
题名
关键词
文摘
作者
第一作者
机构
刊名
分类号
参考文献
作者简介
基金资助
栏目信息

高温氦气实验回路氢气主冷却回路的概念设计

Conceptual Design for Experimental Main Loop with High Temperature Helium Gas
下载PDF
导出
摘要 依据聚变堆包层热工水力实验段的设计要求,并借鉴国内外氦气实验回路的设计和运行经验,对国际热核聚变实验堆(ITER)氦冷固态增殖剂实验包层模块(HCSB-TBM)高温氦气实验主回路进行了概念设计。主要给出了氦气实验主回路(HTHEL)的主要设计参数、回路系统构成及主要设备特点,并对主管道设计进行了应力校核。 Based on the design and running experiences on the helium experimental loops home and abroad, the preliminary conceptual design of the main helium loop, HTHEL, is completed according to the design requirements on TBM experimental section. The main design parameters, the systdm constitutes and main component characteristics for this loop are presented and the stress check is conducted for the design of main pipeline.
作者 马丽华 冯开明 叶兴福 陈焕新
机构地区 核工业西南物理研究院 华中科技大学
出处 《核动力工程》 EI CAS CSCD 北大核心 2009年第2期62-64,74,共4页 Nuclear Power Engineering
关键词 TBM 主回路 概念设计 管路 TBM, Main loop, Conceptual design, Pipeline
分类号 TL424 [核科学技术—核技术及应用]
  • 相关文献

参考文献7

  • 1Rebut P.H. ITER: The First Experimental Fusion Reactor [J]. Fusion Engineering and Design, 1995, 27:3 - 6.
  • 2Aymar R. Status of ITER Project [J]. Fusion Engineering and Design, 2002, 61-62:5 - 12.
  • 3冯开明.ITER实验包层计划综述[J].核聚变与等离子体物理,2006,26(3):161-169. 被引量：52
  • 4Feng K M, Pan C H, Zhang G S, et al, Preliminary Design for a China ITER Test Blanket Module[J]. J of Fusion Engineering and Design, 2006(81): 1219 - 1224.
  • 5Boccaccini L V, Bekris N, Boccaccini L V, et al. Design Description Document for the European Helium Cooled Pebble Bed(HCPB) Test Blanket Modules[R]. Forschungszentrum Karlsruhe, 2005.
  • 6Ghidesa B E. Helium Loop Karlsruhe(HELOKA) - A valuable Tool for Testing and Qualifying ITER Components and Their He Cooling Circuits[J]. Fusion Eng. Des. 2006(81): 1471 - 1476.
  • 7魏信利,吴金星.压力容器现代设计与安全技术[M].化学工业出版社,2004.

二级参考文献18

  • 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51

核动力工程
2009年 第2期

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