摘要
利用蒙特卡罗粒子输运程序MCNP,对紧凑型托卡马克(CT)聚变实验堆方案进行了三维中子学计算分析,特别是氚增殖比(TBR)计算。包层采用了氦冷固态包层(HCCB Blanket)概念,选用正硅酸锂(Li_4SiO_4)作为氚增殖剂,铍作为中子倍增剂,低活化铁素体钢为结构材料。给出了不同增殖单元在不同的排列方式下,TBR随增殖单元厚度的变化情况,得到了满足氚自持条件下的初步优化的包层设计方案,给出了相关中子壁负载、能量沉积和功率密度的相关特性结果,为后续热工水力和相关设计分析提供了数据支持。
Using Monte Carlo particle transport code MCNP, the 3D neutronics analysis as well as TBR calculation for high power compact tokamak （CT） test reactor were done. The structure design for helium cooling ceramic breeder （HCCB） blanket was carried out with Li4SiO4, Be and the low activated ferrite steel as the tritium breeder, neutron multiplier and structural material respectively. The variation of TBR vs the breeding unit thickness was simulated, under different breeding unit with different structure arrangement. The preliminary optimum design of blanket with tritium self-sufficiency was obtained. The related characteristics of neutron wall loading, energy deposit and power density was given, as supplies data support for the thermal hydraulics and related design and analysis in next step.
出处
《核聚变与等离子体物理》
CAS
CSCD
北大核心
2015年第4期327-333,共7页
Nuclear Fusion and Plasma Physics
基金
国家磁约束核聚变能发展研究专项(2014GB110004)
