超临界水冷固态实验包层中子学与热工水力特性研究

基于国际热核聚变实验堆(ITER)实验包层方案,提出了一个超临界水冷固态实验包层概念设计方案。设计采用Be作为中子倍增剂,Li4SiO4作为氚增殖剂,CLAM钢作为结构材料。包层第一壁采用多层盘道设计以提高第一壁出口温度,内部采用增殖剂与中子倍增剂分层布置以提高热沉积与氚增殖率。为验证包层设计的可行性,分析计算了三维包层氚增殖率与热沉积的分布,然后根据中子学计算得到的结果对超临界水冷固态实验包层进行了数值模拟研究。结果表明:包层功率密度分布较合理;氚增殖率满足运行中氚自持的要求;在冷却剂出口温度达到500℃条件下材料温度不超过限值。该设计方案能满足中子学设计与热工水力的要求。

Neutronics and Thermo-hydraulic Characteristic Studies of Supercritical Water Cooled Solid Breeder Test Blanket Module

A conceptual supercritical-water cooled solid breeder test blanket module (SWCB-TBM) design was carried out based on the ITER test blanket project. The SWCB-TBM used the beryllium pebbles as neutron multiplier, Li₄SiO₄ lithium ceramic pebbles as tritium breeder, CLAM steel as the structure material respectively. For enhancing the outlet temperature, the first wall adopted the design of multi-channel in each circuit to increase temperature of outlet, and arranged the breeder and neutron multiplier by layers to increase heat deposition and tritium breeding ratio (TBR). In order to verify the feasibility of the SWCB-TBM, the distributions of the three dimensional TBR and thermal deposition were calculated, and the numerical simulation of SWCB-TBM combining with results of neutronics calculation was also carried out. The results show that the power density distribution of the SWCB-TBM is reasonable. The TBR could meet the requirements for tritium self-sufficiency and the SWCB-TBM components are effectively cooled below the allowable temperature while the temperature of outlet reaches 500 ℃. The design of SWCB-TBM in this paper is reasonable under neutronics and thermal hydraulic conditions.