聚变-裂变混合堆设计研究

Design Research of Fusion-Fission Hybrid Reactor

利用MCNP5和MONK9A程序对聚变驱动裂变混合堆进行了初步研究,在等离子体第1壁外侧依次包覆长方体形状的燃料组件和产氚组件,形成裂变堆芯包层和产氚区。对分别装载贫铀、天然铀、贫铀MOX和天然铀MOX等4种燃料的混合堆进行了研究分析,其中,后两种燃料在整个运行寿期内的功率放大倍数和氚增殖比满足设计要求。通过随燃耗变化的同位素含量分析,初步探讨了混合堆的铀-钚燃耗循环策略。

The preliminary studies on the fusion-fission hybrid reactor were performed with the MCNP5 and MONK9A codes. The cuboid fuel assemblies and tritium-generat-ing assemblies placed in sequence on the outside of the first-wall of the plasma formed the fission zones and tritium-generating zones. Studies were done on the fusion-fission hybrid reactor loaded with depleted uranium fuel, natural uranium fuel, depleted uranium MOX fuel and natural uranium MOX fuel, respectively. The power-amplifier factor and the tritium-generating factor can satisfy the design criteria throughout the cycle when using the last two types of fuel. A uranium-plutonium fuel cycle strategy for the fusion-fission hybrid reactor is preliminarily discussed based on the analysis of isotopic content change versus the burnup.