Development of Fusion reactor Materials

在结构材料上涂覆陶瓷涂层可以有效地降低氚渗透、腐蚀和聚变包层中的MHD压降。本研究通过NIFS、U。东京和IPP-Garching。2001年，利用IPP Garching的电弧源等离子体涂层设备，在NIFS（NIFS-Heat-2）中制备的高纯V-4Cr-4 Ti上涂覆AlN。涂层的强度随着杂质氧含量的降低而增加。2002年，在V-4Cr-4 Ti上进行了Er_2O_3涂层的尝试，并确定了涂层的最佳条件。2003年，对V-4Cr-4 Ti上的Er 2 O3涂层进行了表征，包括X射线衍射、与熔融锂的相容性和氘渗透性。结果表明，当衬底温度超过500 ℃时，涂层具有较高的结晶度和较好的上级Li相容性及氘扩散抑制性能。涂层后在500 ℃以上的退火也导致了结晶度和性能的提高。2004年，在V-4Cr-4 Ti合金上制备了Er_2 O_3涂层，并进行了原位电阻率测试。双层涂层（V或Fe/Er_2 O_3/衬底）在Li至600 ℃下显示出足够的绝缘性能。2005年，正在总结总体成果。

Ceramic coating on structural materials can be effective in reducing tritium permeation, corrosion and MHD pressure drop in fusion blanket. In this study, a new coating with high speed on large area has been fabricated and characterized as MHD insulator and tritium diffusion barrier coating for fusion application, by collaboration of NIFS, U. Tokyo and IPP-Garching. In 2001, high purity V-4Cr-4Ti fabricated in NIFS (NIFS-Heat-2) was coated with AlN using Arc-Source Plasma Coating Facility of IPP-Garching. The strength of the coating increased with reducing the impurity oxygen level. In 2002, coating with Er2O3 was attempted on V-4Cr-4Ti, and the optimum condition for the coating was identified. In 2003, characterization of the Er2O3 coating on V-4Cr-4Ti was carried out including X-ray diffractometry, compatibility with molten lithium and deuterium permeability. The results showed that by keeping the substrate temperature exceeding 500C, the coating has high crystallinity and superior Li compatibility and deuterium diffusion suppression. The post-coating annealing above 500C also resulted in the increased crystallinity and performances. In 2004, Er2O3 coating on bowl-shaped V-4Cr-4Ti was carried out for testing in-situ resistivity in liquid Li. The dual coating, (V or Fe/Er203/Substrate) showed enough insulation property in Li to 600C. In 2005, overall results are being summarized.