聚变-裂变增殖堆包层的初步中子学设计

 基于国际热核实验堆ITER的堆芯参数和套管结构,对聚变-裂变增殖堆包层的进行了初步中子学设计。基于国际热核实验堆的堆芯参数提出了采用套管结构,以天然金属铀为燃料和硅酸锂为氚增殖剂的快裂变-增殖堆包层的初步中子学设计设计方案。使用FENDL 2.1核数据库及MCNP程序自带的核数据库,用MCNP程序对套管结构快裂变-增殖堆包层进行一维的方案筛选及三维中子学的计算分析。计算分析包层内的一维功率密度分布、产氚率、钚增殖率分布,通过优化设计分析给出合理的包层设计方案,并计算氚增殖率TBR、能量放大倍数M、有效增值系数k_eff、裂变增殖比等参数。

Preliminary Neutronics Design of Breed Blanket for Fusion-fission Hybrid Reactor

A preliminary neutronics design of breed blanket for fusion-fission hybrid reactor has been carried out based on the plasma parameters of International Thermonuclear Experimental Reactor (ITER) and casing structure. In the design of fast-fission breed blanket, the natural Uranium pebble bed is used as fuel and neutron multiplication and the Lithium silicate pebble bed is used as tritium breed material. By using FENDL21 nuclear database cross section library with native cross section library of MCNP nuclear database, the calculation and analysis are carried out with MCNP program. Through one-dimension calculation and analysis on different design proposals, a proper design proposal has been screened and then the three-dimension calculation and analysis have been implemented with the parameters of ITER. The calculation shows that the TBR of fusion-fission hybrid reactor is 1.13, it indicates that the design of breed blanket is able to meet self-sustaining of tritium and the calculation also indicates that the energy enlargement of fusion-fission hybrid reactor is 6.5 and Polonium breeding rate is 1.35, it means that the reactor is able to also product large quantities energy and Polonium and they could be used by light water reactor. Meanwhile, fission-breed ratio, power distribution, tritium production rate distribution, Polonium breeding distribution of blanket blocks, and blanket block 14 are also calculated and acquired.