期刊文献+

聚变示范堆气体注入系统氚渗透分析

Tritium permeation of gas injection system for DEMO
下载PDF
导出
摘要 以中国聚变工程实验堆(CFETR)的堆芯参数为例,参照ITER的相关工程设计,对聚变示范堆(DEMO)气体注入系统(GIS)作出了初步的管道布局考虑。基于此布局,计算了稳态运行下GIS含氚管道气流压降,对燃料储存与输运系统的泵压头提出了要求,得出相应泵压头下GIS的氚渗透量。计算结果表明,重力势是管道气流压降的主要原因,在负压情况下,GIS的氚渗透对整体氚循环的影响不大。这为研究DEMO的氚自持问题提供了相关参数,为GIS歧管布局的进一步优化奠定了基础。 In the present work, tritium permeation issue of gas injection system (GIS) in DEMO were focused. Based on the reactor core parameters of Chian Fusion Engineering Test Reactor (CFETR) and referring to accumulated experience of GIS design in ITER, preliminary pipes layout of DEMO GIS was performed. Steady-state tritium gas pressure drop calculation along the pipes and pump head request to the fuel storage and delivery system were made on the basis of the GIS’s structure layout. Tritium permeation under corresponding pump head was calculated at the same time. According to the calculation results, gravitational potential is the main determinant to pressure drop in pipe flow and the tritium permeation in GIS is of little amount to the whole tritium cycle in the case negative pressure. So this work offers related parameters to tritium self-sufficiency issues in DEMO, and also lays the foundation for further optimization of GIS’s structure layout.
出处 《核聚变与等离子体物理》 CAS CSCD 北大核心 2014年第3期240-246,共7页 Nuclear Fusion and Plasma Physics
基金 国际热核聚变实验堆(ITER)计划专项(2011GB11101)
关键词 聚变示范堆 气体注入系统 压降计算 氚渗透 DEMO Gas injection system Pressure drop calculation Tritium permeation
  • 相关文献

参考文献8

  • 1Abdou M, Vold E L, Gung C, et al. Deuterium-tritium fuel self-sufficiency in fusion reactors [J]. Fusion Technology, 1986, 9(2): 250-285.
  • 2江涛,李波,李伟,王明旭.ITER送气系统穿透结构设计[J].核聚变与等离子体物理,2010,30(1):76-81. 被引量:2
  • 3Tao Jiang, Bo Li. Manifold concept design for ITER gas injection system [J]. Plasma Science, 2012, 40(3): 788-792.
  • 4李炜等.水力计算手册[M].武汉:中国水利水电出版社,2006.65-70.
  • 5王玉贵.气体快速注入实验[J].真空科学与技术,1984,6(2):39-44.
  • 6冯春华,房同珍,王龙,杨宣宗,黄建国,陈朝峰,韩建伟,孙远程.等离子体驱动碎片加速器中脉冲充气电磁阀[J].核聚变与等离子体物理,2011,31(2):181-185. 被引量:4
  • 7Li W, Li B, Maruyama S, et al. A description of the ITER's gas injection systems and current R&D activities [J]. Fusion Engineering and Design, 87(5-6): 813-821.
  • 8Thornton A J, Chapman I T. Plasma profile evolution during disruption mitigation via massive gas injection on MAST [J]. Nucl. Fusion, 2012, 52(6): 63018-63029.

二级参考文献13

  • 1韩建伟,张振龙,黄建国,李小银,陈赵峰,全荣辉,李宏伟.利用等离子体加速器发射超高速微小空间碎片的研究[J].航天器环境工程,2006,23(4):205-209. 被引量:15
  • 2Li Wei, Li Bo. Recent progress of GIS/GDC design and manufacturing for ITER [A]. 22^nd IAEA Fusion Energy Conference [C]. 2008, IT/P7-15, P215.
  • 3ITER design documents. Design work order DWO-18-104-YYG-CN [R]. ITER International Team, 2008.
  • 4ITER design documents. Project integration document[R]. ITER International Team, 2007.
  • 5ITER design documents. INTERFACE SHEET IS-31- 15-002, Interface sheet between GIS and VV [R]. ITER International Team, 2008.
  • 6ITER design documents. ITER Vacuum Handbook V1.1[R]. ITER International Team, 2008.
  • 7Maruyama S, Yang Y. GIS leak detection, ITER documents [R]. ITER International Team, 2008.
  • 8ITER design documents. ITER material properties handbook V1.0 Part 1 [R]. ITER International Team, 2008.
  • 9ITER design documents. Load specifications for the/TER vacuum vessel [R]. ITER International Team, 2008.
  • 10Thomas P, Igenbergs E, Tamura H, et al. Theoretical investigation of the plasma dynamic accelerator [J]. IEEE Tran. Magnet, 1993, 29(1): 609-614.

共引文献4

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