Tritium permeation and retention are serious problems in D-T fusion reactors from the viewpoint of fuel efficiency and radiological safety. Functional ceramic coatings have been intensively studied for the development of tritium permeation barriers for several decades, while reports about tritium retention in the ceramic coatings are scarce. Moreover, irradiation may affect tritium retention in fusion materials, which is important to precisely evaluate tritium inventory in the reactor. In this study, the gamma-ray irradiation effect on deuterium retention in reduced activation ferritic/martensitic steel and three kinds of ceramic coatings were investigated through deuterium exposure, gamma-ray irradiation using cobalt-60 gamma-ray sources and deuterium depth profile measurements. The amount of deuterium retention in yttrium oxide, silicon carbide, and zirconium oxide coatings decreased after the irradiation in the dose rate of 2.43 Gy s⁻¹, while no clear change in the retention was observed at the lower dose rate. From these results, the gamma-irradiation effect on deuterium retention would have a threshold dose rate. Diffusion and desorption of deuterium would be accelerated by excitation of deuterium via energy transfer from electrons generated by Compton scattering.

从燃料效率和放射学安全性的角度来看，fusion聚变反应堆中Tri的渗透和保留是严重的问题。数十年来，对功能陶瓷涂层进行了深入研究以开发t渗透屏障，而有关reports在陶瓷涂层中保留的报道却很少。此外，辐射可能会影响fusion在聚变材料中的保留，这对于精确评估反应堆中的inventory存量很重要。在这项研究中，通过氘暴露，使用钴60γ射线源进行的γ射线辐照和氘深度测量，研究了γ射线辐照对还原活化铁素体/马氏体钢和三种陶瓷涂层中氘保留的影响。氧化钇，碳化硅，^-1，而在较低剂量率下未观察到保留的明显变化。根据这些结果，γ射线对氘保留的影响将具有阈值剂量率。氘的扩散和解吸将通过由康普顿散射产生的电子通过能量转移激发氘而加速。