This article covers the investigation of tritium release and retention properties of beryllium pebbles with diameters of 0.5 and 1 mm after neutron irradiation at temperatures of 643-923 K and damage doses of 21-37 dpa corresponding to 3632-5925 appm helium and 367-644 appm tritium productions, respectively. The thermos-desorption spectra have a single main peak for both tritium and helium release. The peak temperatures at both used heating rates of 0.017 K/s and 0.117 K/s are in the range of 1052-1364 K for tritium and 1104-1336 K for helium release. The peak temperatures at a heating rate of 0.017 K/s are always lower than at 0.117 K/s. The tritium retention in both 0.5 and 1 mm beryllium pebbles considerably decreases by increasing irradiation temperature reaching of 1-18 % at the highest temperature of 923 K regardless of the pebble diameter. Open channels are formed in the beryllium pebble microstructure at high irradiation temperatures. These microstructural features contribute to the enhanced release and low retention in beryllium pebbles under neutron irradiation.

本文涵盖了在643-923 K的温度下中子辐照以及损伤剂量为21-37 dpa（对应于3632-5925 appm的氦气和367-644）后直径为0.5和1 mm的铍卵石的of释放和保留特性的研究。分别生产appm tri。对于s和氦的释放，热解吸光谱具有一个主峰。在两种使用的加热速率分别为0.017 K / s和0.117 K / s的情况下，for的峰值温度在1052-1364 K，氦气释放的峰值温度在1104-1336K。加热速度为0.017 K / s时的峰值温度始终低于0.117 K / s。不管卵石直径如何，在最高的923 K温度下增加1-18％的辐照温度，0.5在0.5和1 mm铍卵石中的retention保留量都会大大降低。在高辐照温度下，铍卵石微结构中形成了开放通道。这些微结构特征有助于在中子辐照下提高铍卵石的释放和低保留率。