欢迎访问《核聚变与等离子体物理》官方网站,今天是 分享到:

核聚变与等离子体物理 ›› 2019, Vol. 39 ›› Issue (4): 301-308.DOI: 10.16568/j.0254?6086.201904003

• 核聚变工程技术 • 上一篇    下一篇

水冷陶瓷增殖剂包层氚输运分析

张 兵1, 2,赵雪丽1, 2,马学斌3, 4,刘松林1   

  1. (1. 中国科学院等离子体物理研究所,合肥 230031;2. 中国科学技术大学,合肥 230026; 3. 深圳大学新能源研究中心,深圳 518060;4. 深圳大学光电工程学院,深圳 518060)
  • 收稿日期:2018-08-02 修回日期:2019-07-08 出版日期:2019-12-15 发布日期:2019-12-16
  • 作者简介:张兵(1993-),湖北十堰人,硕士研究生,从事核能与核技术工程研究。
  • 基金资助:

    国家重点研发计划(2017YFE0300502)

Tritium transport analysis for water cooled ceramic breeder blanket

ZHANG Bing1, 2, ZHAO Xue-li1, 2, MA Xue-bin3, 4, LIU Song-lin1   

  1. (1. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031; 2. University of Science and Technology of China, Hefei 230026; 3. Advanced Energy Research Center, Shenzhen University, Shenzhen 518060; 4. College of Optoelectronic Engineering, Shenzhen University, Shenzhen 518060)
  • Received:2018-08-02 Revised:2019-07-08 Online:2019-12-15 Published:2019-12-16

摘要:

基于2015版本中国聚变工程实验堆(CFETR)水冷陶瓷增殖剂(WCCB)包层模块设计特点,建立详细的氚输运分析模型,对不同包层模块(包括不同的增殖区)、载氚气回路、冷却剂回路和蒸汽发生器中的氚输运进行分析。结果表明不同包层模块氚的浓度、渗透量、滞留量均不同,全堆所有包层模块增殖区中氚的滞留量为6.62×10-2g,结构材料中氚滞留量为2.01g,载氚气和冷却剂回路中氚滞留量分别为4.03×10-4g和0.19g,氚通过蒸汽发生器的渗透量为20mg×y-1,冷却剂回路中氚渗透到管道外的量为0.1mg×y-1

关键词: 中国聚变工程实验堆, 水冷陶瓷增殖剂包层, 氚分析

Abstract:

Based on the design of the 2015 version of China Fusion Engineering Test Reactor (CFETR) water cooled ceramic breeder (WCCB) blanket modules surrounding the plasma, a tritium transport model has been developed. Tritium transport analysis has been carried out for each blanket module with different breeding zones, purge gas loop, coolant loop and steam generator. The results indicate that the concentration, permeability and retention of tritium among blanket modules are different. For all of the WCCB blanket modules in CFETR, the tritium retention inside the breeder is 6.62×10-2g, the tritium retention inside the structural materials is 2.01g, the tritium retention inside purge gas and coolant loop are 4.03×10-4g and 0.19g respectively, the tritium permeation through the steam generator tube walls is 20mg•y-1, the tritium permeation from the coolant pipes is 0.1mg•y-1.

Key words: CFETR, Water cooled ceramic breeder blanket, Tritium analysis

中图分类号: