球环型产氚聚变堆中子学分析  

Neutronics analysis of tritium production fusion reactor based on the spherical torus

作　　者：何开辉[1] 黄锦华[1] 冯开明[1] 

机构地区：[1]核工业西南物理研究院,成都610041

出　　处：《核聚变与等离子体物理》2004年第2期152-156,共5页Nuclear Fusion and Plasma Physics

摘　　要：对球环型产氚聚变堆概念设计中的中子学设计进行了计算分析。此设计利用了球形环的先进等离子体物理性能和紧凑的结构特征,并尽量利用真空室内的空间安置氚生产包层以减少氚泄漏而提高氚增殖率,达到年产氚量1kg的目标。2D中子学计算得到的氚增殖率高于1 68的设计是其它类似设计没有达到的,进一步体现出球环型产氚聚变堆的先进性。Conceptual design of an advanced tritium production reactor based on spherical torus (ST) is presented in this paper.Different from traditional tokamak tritium production reactor design,advanced plasma physics performance and compact structural characteristics of ST were used to minimize tritium leakage and to maximize tritium breeding ratio with arrangement of tritium production blankets as possible as it can be placed within vacuum vessel in order to produce 1kg excess tritium,corresponding plant availability 40% or more.The tritium breeding ratio obtained from 2D neutronics calculation,as high as 1.68, has not yet been available in previous tritium production reactor design.It shows that tritium production based on the ST is more advanced than other ways.

关 键 词：球环型 产氚聚变堆 中子学分析 氚增殖率 

分 类 号：TL613[核科学技术—核技术及应用]