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首页> 外文会议>Proceedings of the 9th China-Japan Symposium(CJS-9) on Materials for Advanced for Energy Systems and Fission amp; Fusion Engineering Jointed with CAS-JSPS Core-university Program Seminar on Fusion Materials, System and Design Integration >Preliminary Analysis on Tritium Permeation through the First Wall of China DFLL-TBM for ITER
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Preliminary Analysis on Tritium Permeation through the First Wall of China DFLL-TBM for ITER

机译：I透ITER DFLL-TBM第一壁的Per渗透率初步分析

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摘要

The tritium permeation through the First Wall (FW) from plasma into helium coolant had been evaluated for the Dual-Functional Lithium-Lead Blanket Module (DFLL-TBM). The influence of surface conditions on plasma facing and coolant sides, temperature gradient, beryllium layer clad on the plasma facing side, and trapping in defects on the tritium permeation had been considered. The results show that most of the tritium implanted in the FW re-entered into the plasma. The plasma-driven tritium permeation was very sensitive to the surface conditions on plasma facing side. With a higher sticking coefficient on the plasma-facing side, the tritium permeation into helium coolant was reduced largely. The tritium permeation was strongly reduced with a beryllium layer clad on the front side of the FW. The plasma driven tritium permeation will not seriously influence the tritium safety of DFLL-TBM. Based on tritium safety, it's reasonable to clad beryllium layer on the FW and keep the surface clean to reduce the plasma dr riven tritium permeation.
机译：对于双重功能锂铅毯模块（DFLL-TBM），已经评估了plasma从第一壁（FW）从等离子体渗透到氦冷却剂中的情况。已经考虑了表面条件对等离子面对和冷却剂侧，温度梯度，铍层覆盖在等离子面对侧上以及and缺陷渗透中的缺陷捕获的影响。结果表明，植入到FW中的大多数the都重新进入了等离子体。等离子体驱动的ium渗透对面向等离子体侧的表面条件非常敏感。由于在面对等离子体的一面具有更高的粘附系数，largely进入氦冷却剂的渗透大大降低了。 F的前侧覆有铍层，大大降低了per的渗透率。等离子体驱动的ium渗透不会严重影响DFLL-TBM的safety安全性。基于tri的安全性，合理的做法是在铍玻璃上覆盖铍层并保持表面清洁，以减少等离子体对tri的渗透。

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