The accurate prediction of tritium inventory and permeation fluxes in the breeding blanket of a D-T fusion reactor is a key aspect for future thermonuclear power plants licensing. Tritium permeation into structural materials could give rise to potential issues concerning the fuel self-sufficiency and can be lost into the environment with resulting radiological risks for the population. In the frame of hydrogen isotopes transport modelling, the Tritium Migration Analysis Program (TMAP) code is considered a referred code for the safety design of nuclear fusion power plants. It is mainly applied to Plasma Facing Components (PFCs), which are subjected to intense particles implantation and surface heat fluxes.

中文翻译：

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通过 TMAP 验证和验证 mHIT 代码，用于聚变相关环境中的氢同位素输运研究

准确预测 DT 聚变反应堆增殖层中的氚库存和渗透通量是未来热核电站许可的一个关键方面。氚渗透到结构材料中可能会引起有关燃料自给自足的潜在问题，并且可能会流失到环境中，从而对人群造成放射性风险。在氢同位素输运建模框架中，氚迁移分析程序（TMAP）代码被认为是核聚变电厂安全设计的参考代码。它主要应用于等离子体表面组件（PFC），这些组件受到强烈的粒子注入和表面热通量的影响。