期刊文献+

CFETR氦冷固态增殖剂包层产氚性能研究及优化 被引量:5

Study and Optimization on Tritium Production Performance of CFETR Helium Cooled Solid Breeder Blanket
下载PDF
导出
摘要 氦冷固态增殖剂包层是中国聚变工程实验堆(CFETR)的3种候选包层概念之一。本文基于中国核工业西南物理研究院提出的一种氦冷固态增殖剂包层概念,通过蒙特卡罗输运程序MCNP5建立了包层三维中子学模型,探究了不同几何布置方案及结构设计参数对包层产氚性能的影响,得到了全堆氚增殖比(TBR)及极向各包层模块产氚分布,并由优化后的模型得到了包层模块核热分布。结果表明,优化后的TBR达到1.177,满足氚自持的最低要求。 The helium cooled solid breeder blanket is one of the three candidate blanket concepts of Chinese Fusion Engineering Test Reactor(CFETR).Based on the concept of helium cooled solid breeder blanket proposed by Southwestern Institute of Physics,the three-dimensional neutronic model of CFETR helium cooled solid breeder blanket was established by Monte Carlo transport program MCNP5,and the effects of different geometric arrangement schemes and structural parameters on tritium breeding ratio(TBR)and the TBR in each blanket module were obtained.The results show that the optimized TBR reaches 1.177 and meets the requirement of tritium self-sufficiency.
作者 张宝锐 解衡 郎明刚 孙倩 ZHANG Baorui;XIE Heng;LANG Minggang;SUN Qian(Institute of Nuclear and New Energy Technology,Tsinghua University,Beijing 100084,China)
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2018年第9期1649-1655,共7页 Atomic Energy Science and Technology
基金 国家科技计划课题国际热核聚变实验堆(ITER)计划专项资助项目(2014GB114000)
关键词 CFETR 氦冷固态增殖剂包层 TBR CFETR helium cooled solid breeder blanket TBR
  • 相关文献

参考文献2

二级参考文献70

  • 1Liu Y L, Zhang Y, Lu G H, et al. Vacancy Trapping Mechanism for Hydrogen Bubble Formation in Metal[ J]. Phys Rev B, 2009, 79:172 103.
  • 2Zhou H B, Liu Y L, Lu G H, First-Principles Investigation Energetics and Site Preference of He in a W Grain Boundary [ J ]. Nucl Instrum Methods Phys Res B, 2009, 267:3 189 -3 192.
  • 3Atkhamees A, Liu Y L, Lu G H, et al. First-Principles Investigation on Dissolution and Diffusion of Oxygen in Tungsten[ J]. NuclMater, 2009, 393: 508-512.
  • 4Yu Y W, Gao X,Hu J S, et al. ECR Discharge Cleaning and Followed He GDC on HT-7 Tokamak[J]. Nucl Mater, 2009, 390-391:1 051-1 054.
  • 5Gao X, Hu J S, Zhao Y P, et al. ICRF Wall Conditioning and Plasma Performance on EAST [ J]. Nucl Mater, 2009, 390 - 391:864 -868.
  • 6ITER International Organization. ITER[ EB/OL]. (2006 - 11 - 21)[2009-10-213. http: //www. iter. org.
  • 7EAST Big Science Engineering. EAST Experimental Device Smoothly Passed Acceptance Inspection [ EB/OL] (2006 - 08 -11)[2009-10-21]. http: //east. ipp. ac. cn.
  • 8Shimada M, Costley A E, Federici G, et al. Overview of Goals and Performance of ITER and Strategy for Plasma-Wall Interaction Investigation[ J]. Nucl Mater, 2005, 337 : 808 - 815.
  • 9Bolt H, Barabash V, Krauss W, et al. Materials for Plasma-Fa- cing Components of Fusion Reactors [ J ]. Nucl Mater, 2005, 329-333: 67-73.
  • 10Neu R, et al. 20^th IAEA Fusion Energy Conference[ C]. Vilamoura: Portugal, 2004.

共引文献29

同被引文献35

引证文献5

二级引证文献16

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