Abstract Titanium beryllide is considered as an advanced neutron multiplier in the Helium Cooled Pebble Bed (HCPB) blanket of DEMO. Neutron irradiation of titanium beryllide together with beryllium as a reference material in material testing nuclear reactors can give essential data for the DEMO blanket design. Be-7at.%Ti (Be-7Ti) as well as Be were irradiated in the HFR, Petten, the Netherlands, at four temperatures of 710, 800, 940, 1040 K up to 23, 31, 36, 38 dpa, respectively. The post-irradiation examination (PIE) included thermal-programmed desorption (TPD) and Vickers hardness tests as well as microstructure study by optical metallography. Be and Be-7Ti pellets maintained their integrity after irradiation. Microstructure of Be-7Ti contains two phases, mainly, TiBe12, and also small amount of Be. Under irradiation, gas bubbles were formed in Be samples as well as in Be-phase in Be-7Ti samples. These bubbles contain helium and tritium produced in Be under irradiation. TPD tests showed a much lower tritium retention in Be-7Ti than in Be for all four irradiation temperatures. Vickers hardness of TiBe12 phase is much higher than that of Be-phase. According to the obtained data, Be-7Ti could be considered more preferred than Be as a neutron multiplier material in future fusion reactors due to the enhanced radiation damage resistance.

中文翻译：

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中子辐照损伤剂量为 23-38 dpa 后氚在铍和铍化钛中的释放和滞留

摘要 在DEMO的氦冷球床（HCPB）毯中，铍化钛被认为是一种先进的中子倍增器。在材料测试核反应堆中作为参考材料的铍化钛和铍的中子辐照可以为 DEMO 覆盖层设计提供基本数据。Be-7at.%Ti (Be-7Ti) 和 Be 在荷兰佩滕的 HFR 中分别在 710、800、940、1040 K 四个温度下辐照，分别达到 23、31、36、38 dpa . 辐照后检验 (PIE) 包括热程序解吸 (TPD) 和维氏硬度测试以及通过光学金相学进行的微观结构研究。Be 和 Be-7Ti 颗粒在辐照后保持其完整性。Be-7Ti 的显微组织包含两相，主要是 TiBe12，也有少量 Be。在辐照下，在 Be 样品以及 Be-7Ti 样品的 Be 相中形成了气泡。这些气泡含有在 Be 辐照下产生的氦和氚。TPD 测试表明，在所有四种辐照温度下，Be-7Ti 中的氚保留率远低于 Be。TiBe12 相的维氏硬度远高于 Be 相。根据获得的数据，由于增强的抗辐射损伤能力，在未来的聚变反应堆中，Be-7Ti 可以被认为比 Be 更优选作为中子倍增材料。