Study on Tritium Production Using a High-Temperature Gas-Cooled Reactor for Fusion Reactors: Evaluation of Tritium Outflow by Non-Equilibrium Diffusion Simulations
Study on Tritium Production Using a High-Temperature Gas-Cooled Reactor for Fusion Reactors: Evaluation of Tritium Outflow by Non-Equilibrium Diffusion Simulations
复制标题
聚变反应堆高温气冷堆制氚的研究：非平衡扩散模拟评价氚流出
DOI：
10.1080/15361055.2017.1352424
复制
发表时间：
2017
影响因子：
0.9
通讯作者：
Minoru Goto and Shigeaki Nakagawa
中科院分区：
文献类型：
--
作者：
Satoru Nagasumi;Hideaki Matsuura;Kazunari Katayama;Teppei Otsuka;Minoru Goto and Shigeaki Nakagawa
研究了利用高温气冷堆（HTGR）为聚变堆生产氚的性能。从氚回收和环境安全的角度来看，从锂棒流出的氚应该被抑制到与日本压水反应堆（PWR）的液体放射性废物相同的水平。研究了抑制锂棒氚泄漏的方法。在非平衡态模拟的基础上，对氚的流出进行了精确的重新评估，并阐明了冷却剂温度对氚泄漏的影响。本文还研究了在锂棒中加入锆以降低氚压力的方法以及由此产生的抑制氚泄漏的效果，非平衡模拟结果表明，氚流出量比以前的研究报告中的流出量低约40%。虽然发电效率降低，但冷却剂温度降低到600 K导致氚流出量与冷却剂温度为800 K的情况下的流出量相比减少到约1/30。在日本的PWR中，在Li棒中加入Zr可以将氚流出量（与不含Zr的情况相比，约为1/200）抑制到流出水平以下。
Performance of tritium production for fusion reactors, using a high-temperature gas-cooled reactor (HTGR) is examined. From the viewpoints of tritium recovery and environmental safety, tritium outflow from Li rods should be suppressed to the same level as the liquid radioactive waste from the pressurized water reactors (PWRs) in Japan. Methods for suppressing tritium leakage from Li rods are studied. The tritium outflow is reevaluated accurately on the basis of non-equilibrium simulations and the influence of coolant temperature on tritium leakage is clarified. The approach using Zr in the Li rod to reduce the tritium pressure and the resulting suppression of tritium leakage are also investigated.The results of the non-equilibrium simulation show that the tritium outflow is approximately 40% lower than the outflow reported in a previous study. Although the electric power generation efficiency is reduced, lowering the coolant temperature to 600 K results in a reduction of the tritium outflow to ~1/30 compared to the outflow in the case of a coolant temperature of 800 K. The incorporation of Zr into the Li rod can suppress tritium outflow (to ~1/200 compared to the case without Zr) to below the outflow level in PWRs in Japan.