MCORGS及次临界能源堆包层概念研究进展

次临界能源堆是以能源供应为目的的一种聚变裂变混合堆,以聚变驱动,天然铀为裂变燃料,轻水为冷却剂。本文针对该混合堆开发了基于MCNP与ORIGENS的三维中子输运燃耗耦合程序MCORGS,分析了包层三维中子学模型。提出简化干法后处理,设想利用衰变热将乏燃料加热到2 100K,将沸点低于该温度的裂变产物挥发去除。计算了包层各区材料每年发生的原子移位数,建议采用10a左右的换料周期,乏燃料经后处理后可多次复用。第1个寿期内氚增殖比TBR平均约1.15,包层能量放大倍数M平均约12;第2~9个寿期内TBR平均约1.35,M平均约18。利用流体动力学程序完成了包层CAD模型建立、网格划分及稳态传热计算分析,各区材料的最高温度均低于许用温度并有较大裕量。

Progess in MCORGS Code and Blanket Conceptual Research on Fusion Fission Hybrid Reactor for Energy

Fusion fission hybrid reactor for energy (FFHR E) is fueled by natural uranium and cooled by light water. A three dimensional code MCORGS, which is coupled by MCNP and ORIGENS, has been adopted in neutronics analysis of the three dimensional blanket model for FFHR-E. An simplified pyro-reprocessing scheme was suggested. It is expected that the spent fuel can be heated up to 2 100 K by its decay heat, then the fission product elements whose boiling points below this temperature will be evaporated. The displacement per atom (dpa) of the blanket materials was evaluated. A reload period around ten years is suggested, and the spent fuel can be reused multiple times after reprocessing. The average tritium breeding ratio (TBR) is about 1.15 and the blanket energy multiplication is about 12 in the first fuel reload cycle. While in the 2nd to 9th fuel reload cycles, the average TBR and M are 1.35 and 18 respectively. Computational fluid dynamics code was used in CAD modeling, meshing, and steady state heat transfer analysis. The maximal temperatures in different zones are all lower than their allowable values and have reasonable margins.