期刊文献+

10^12n/s氘氚聚变中子发生器旋转氚靶设计与传热分析 被引量:2

Design and Heat Transfer Analysis of Rotating Tritium Target of10^(12)n/s D-T Fusion Neutron Generator
下载PDF
导出
摘要 本文设计一种用于1012 n/s量级氘氚中子发生器HINEG(High Intensity Neutron Generator)的旋转氚靶系统,对该系统的技术难点、机械和冷却方案等进行介绍,给出了该靶系统的设计关键指标参数,并利用CFD方法对该旋转靶系统的传热过程进行三维模拟和分析。分析结果表明,该靶系统在稳定运行时,靶片最高温度为48℃,靶系统采用的冷却方案可以有效地实现靶系统的散热,不会发生氚的大量释放和靶片熔毁。 A rotating tritium target used in high intensity neutron generator (HINEG) with 101~ n/s neutron intensity was proposed in this paper. The technical challenges, mechanical and cooling design o{ the rotating tritium target were introduced and the key design limit value was given. The heat transfer process of the rotating tritium target system was simulated and analyzed by CFD method. The results showed that the maximum temperature was about 48℃ when the target system was under steady operation. That means the cooling design can realize the cooling of this rotating tritium target effectively, which makes no release of the tritium and melting of the target.
出处 《核科学与工程》 CSCD 北大核心 2015年第1期13-17,共5页 Nuclear Science and Engineering
基金 中国科学院科研装备研制项目(批准号:Y2010009) 中科院战略性先导科技专项(批准号:XDA03040000) 国家自然科学基金重大研究计划项目(No.91026004)资助的课题
关键词 中子发生器 氘氚聚变 旋转靶 传热分析 neutron generator deuterium-tritium fusion rotating target heat transfer
  • 相关文献

参考文献13

  • 1Ramey D W, Adair H I- Preparation and Characterization of Tritium Targets [J].IEEE Transactions on Nuclear Science, 1983,NS-30(2) :1575-1579.
  • 2Logan C M, Heikkinen D W. RTNS-II-A Fusion Materials Research Tool [J]. Nuclear Instruments and Methods, 1982,200 : 105-111.
  • 3Voronin G, Kovalchuk M, Svinin M, et al. Development of the Intense Neutron Generator SNEG-13 E J']. Proceedings of EPAC 94,1994,3 : 2678-2680.
  • 4Wu Y C,Jiang J Q, Wang M H,Jin M,FDS Team. A Fusion~Driven Subcritical System Concept Based on Viable Technologies [J]. Nuclear Fusion, 2011, 51 (10) :103036.
  • 5Wu Y C, FDS Team. CAD-based interface programs for fusion neutron transport simulat{.on E ] 1. Fusion Engineering and Design,2009,84(7-11):1987-1992.
  • 6Wu Y C, FDS Team. Design status and development strategy of china liquid lithium-lead blankets and related material technology [J].Journal of Nuclear Materials, 2007,367-370 : 1410-1415.
  • 7Wu Y C,FDS Team. Conceptual design activities of FDS series fusion power plants in china E J "]. Fusion Engineering and Design,2006,81(23-24) :2713-2718.
  • 8Wu Y C, FDS Team. Conceptual design and testing strategy of a dual functional lithium-lead test blanketmodule in ITER and EAST [J].Nuclear Fusion, 2007,47 (11) : 1533-1539.
  • 9Wu Y C, FDS Team. Design analysis of the china dual- functional lithium lead (DFLL) test blanket module in ITER [J]. Fusion Engineering and Design, 2007, 82: 1893-1903.
  • 10Wu Y C,OIAN J P,Yu J N. The Fusion-Driven Hybrid System and Its Material Selection [J ]. Journal of Nuclear Materials, 2002,307-311 : 1629-1636.

二级参考文献11

共引文献38

同被引文献22

引证文献2

二级引证文献2

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