磁约束聚变堆次临界包层概念设计研究进展  

Research development on conceptual design of subcritical blanket driven by magnetic fusion reactor

作　　者：黄洪文[1] 彭述明[1] 李正宏[1] 钱达志[1] 马纪敏[1] 郭海兵[1] 刘志勇[1] 曾和荣[1] 王少华[1] 

机构地区：[1]中国工程物理研究院核物理与化学研究所,四川绵阳621900

出　　处：《强激光与粒子束》2015年第12期13-18,共6页High Power Laser and Particle Beams

基　　金：国家磁约束核聚变能研究专项(2012GB106000)

摘　　要：为使磁约束聚变堆实现能量放大与氚自持,在其等离子体区周围设置次临界包层和产氚包层。采用天然铀合金燃料、轻水作冷却剂兼慢化剂,内嵌压力管式的次临界包层设计方案,通过对包层物理性能、结构概念设计、热工水力性能和安全分析,表明该方案可将聚变能量放大10倍以上,氚增殖比大于1.15,具有天然的临界安全性和良好余热安全性能。立足于近中期可利用的聚变技术,力争实现聚变能源的提前商用,为我国能源可持续发展提供一种有竞争力的技术选项。In order to achieve tritium self-sustaining and energy amplification of the magnetic confinement fusion reactors,sub-critical blanket and tritium breeding blanket were set around the plasma region. We adopted natural uranium alloy as fuel,light water as coolant and moderator and embedded pressure tube sub-critical blanket as blanket design. By the analysis of neu-tronic physical properties, structural concept design, thermal-hydraulic performance and reactor safety, it shows that the multiplication factor may reach 10, tritium breeding ratio is greater than 1.15, and the blanket keeps in a deep sub-critical state andshows good heat safety performance. Based on the recently available fusion technology, we are striving to achieve the early com-mercial use of fusion energy and provide a competitive technology options for the sustainable development of China＇s energy.

关 键 词：次临界包层 物理设计 包层结构 热工水力 

分 类 号：TL371[核科学技术—核技术及应用]