Study on tritium production for fusion reactors using high-temperature gas-cooled reactor

提出了采用高温气冷堆（已发展成为具有高安全性能的新一代裂变堆）生产聚变堆氚。假设一个300-MWe标称容量的燃气轮机高温反应堆（GTHTR300） [600MWt]，估计在180天的运行中可以产生0.3~0.7 kg的氚（取决于锂化合物的装载模式和反应堆的运行情况）。找出了高温气冷堆作为氚生产装置的效率，并指出了实现该系统的技术问题。

Tritium production using the high-temperature gas-cooled reactor (which has been developed as a next generation fission reactor with high-level safety performance) for fusion reactors is proposed. When a “gas turbine high-temperature reactor of 300-MWe nominal capacity (GTHTR300) [600MWt]” isassumed, it is estimated that 0.3～0.7 kg of tritium (depending on Li-compound loading patterns and reactor operation scenario)can be produced in 180-day operation. Efficiency of the high-temperature gas-cooled reactor as a tritium productiondevice is found out and the technical issues to realize the system are specified.