Neutron damage in beryllium
Neutron damage in beryllium
复制标题
铍中的中子损伤
DOI：
10.1016/s0022-3115(09)80032-9
复制
发表时间：
1992
影响因子：
3.1
通讯作者：
H. Heinisch
中科院分区：
文献类型：
--
作者：
D. Gelles;H. Heinisch
正在研究中子辐照对铍的机械性能和氦保留的影响，使用辐射后拉伸试验，断口分析和微观结构检查在FFTF/MOTA中辐照的电弧铸造铍，以支持国际热核聚变实验反应堆（ITER）的设计工作。通过在400°C下辐照至8个位移/原子（dpa）使微型片材拉伸试样脆化。零延性破坏同时发生穿晶脆性解理和晶界脆化。基于显微组织检查，脆化归因于晶界处氦泡的形成和c型环的形成。这种类型的环形成在文献中很少报道。在500°C至1 dpa的条件下对相同材料的伴随显微组织检查样本进行辐照。在500°C下辐照的主要影响是氦泡在基质和晶界位错上的发展，但也发现了空隙膨胀开始的证据。
The effects of neutron irradiation on the mechanical properties and helium retention of beryllium are being studied using postirradiation tensile testing, fractography, and microstructural examinations on arc cast beryllium that was irradiated in the FFTF/MOTA to support the International Thermonuclear Experimental Reactor (ITER) design effort. Miniature sheet tensile specimens were embrittled by irradiation at 400°C to 8 displacements per atom (dpa). Failure with zero ductility occurs with both transgranular brittle cleavage and grain boundary embrittlement. Based on microstructural examination, embrittlement is ascribed both to helium bubble formation at grain boundaries and to c-type loop formation. Loop formation of this type has rarely been reported in the literature. Companion microstructural examination specimens of identical material were irradiated at 500°C to 1 dpa. The major effect of irradiation at 500°C is the development of helium bubbles on matrix and grain boundary dislocations, but evidence of the onset of void swelling was also found.