Abstract Recent advances in tritium transport modeling of helium-cooled ceramic breeding blankets systems has shined light into some tritium management issues. A detailed component model accounting for multi-physics, design, and operational features is necessary to provide accurate estimations of tritium permeation rates to the building/environment- a safety and licensing concern for a fusion nuclear reactor. We found that tritium permeation to buildings can be reduced of ∼20 times when H2 is increased from ∼0.2 Pa to 100 Pa in coolant streams due to the effect of H and T co-permeation. Similarly, the practice of adding about 0.1 % vol of H2 into the helium purge gas to promote tritium release can also reduce permeation from breeding zones to coolant systems. However, high H2 partial pressure in helium purge gas further complicates tritium extraction methodology, and may compromise extraction efficiency. This paper provides a concentrated analysis of tritium management in the He-cooled ceramic blankets with the goal of providing further outer fuel cycle tritium R&D guidance from an integrated point of view.

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氚建模的最新进展及其对外燃料循环氚管理的影响

摘要 氦冷却陶瓷育种毯系统氚输运建模的最新进展已经揭示了一些氚管理问题。考虑到多物理场、设计和操作特征的详细组件模型对于提供对建筑物/环境氚渗透率的准确估计是必要的——这是聚变核反应堆的安全和许可问题。我们发现，由于 H 和 T 共同渗透的影响，当冷却剂流中的 H2 从~0.2 Pa 增加到 100 Pa 时，氚对建筑物的渗透可以减少~20 倍。类似地，将大约 0.1% vol 的 H2 添加到氦吹扫气体中以促进氚释放的做法也可以减少从繁殖区到冷却剂系统的渗透。然而，氦吹扫气体中的高 H2 分压使氚提取方法进一步复杂化，并可能影响提取效率。本文对 He 冷却陶瓷毯中的氚管理进行了集中分析，目的是从综合的角度提供进一步的外燃料循环氚研发指导。