Embrittlement caused by tritium and helium produced as the beta-decay product of tritium affects the structural integrity of materials used in nuclear fusion reactors. We assess the embrittlement of 316L stainless steel used as the primary vessel in the tritium storage and delivery system with a planned operation scenario for the International Thermonuclear Experimental Reactor. First, based on the current system design and planned operation scenario, the tritium and helium concentrations in the primary vessel material are calculated. The effects of tritium and helium on the mechanical properties are estimated in comparison with available experimental data. We conclude that, if a forged material is used, the mechanical properties of the primary vessel will not significantly degrade over planned operation in terms of fracture toughness. In addition, fatigue and creep are expected not to be significant. Last, we discuss two possible methods to lower the concentration of helium for the purpose of reducing the residual risk.

由and的β衰变产物产生的and和氦引起的脆化影响核聚变反应堆中所用材料的结构完整性。我们根据国际热核实验反应堆的计划运行情况，评估了storage储存和输送系统中用作主要容器的316L不锈钢的脆化程度。首先，根据当前的系统设计和计划的操作方案，计算出主要容器材料中的and和氦浓度。与现有的实验数据相比，估算了are和氦对机械性能的影响。我们得出的结论是，如果使用锻造材料，则在断裂韧性方面，主容器的机械性能不会超过计划的操作而显着降低。此外，疲劳和蠕变预计不会很大。最后，我们讨论了降低氦气浓度以降低残留风险的两种可能方法。