Low-temperature low-dose neutron irradiation effects on beryllium
Low-temperature low-dose neutron irradiation effects on beryllium
复制标题
低温低剂量中子辐照对铍的影响
DOI：
10.1016/j.jnucmat.2003.12.016
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发表时间：
2004
影响因子：
3.1
通讯作者：
L. Snead
中科院分区：
文献类型：
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作者：
L. Snead
介绍了高质量铍材料在水慢化堆中低温、低剂量中子辐照下的力学性能结果。所选择的材料是由Brush Wellman生产的S-65C ITER候选材料、Kawecki Berylco Industries生产的P0铍和高纯度区域精制铍。在橡树岭国家实验室的高通量同位素反应堆（HFIR）和布鲁克海文国家实验室的高通量束反应堆（HFBR）中，在~ 100-300°C的温度范围内，用快速（E>0.1 MeV）中子通量0.05-1.0×1025n /m2辐照了微型薄片拉伸和热扩散试样。正如早期对铍的研究所预期的那样，两种材料都经历了显著的拉伸脆性，相应的塑性降低和强度增加。测量了热扩散率和体积膨胀，发现在这个温度和流量范围内的变化可以忽略不计。这项工作的重要意义在于，虽然这两种材料在ITER相关的辐照条件下都会迅速脆化，但仍有一些延展性（1-2%），这与早期的工作形成对比，包括最近对Brush-Wellman S-65C材料辐照到略高中子通量的工作。
Mechanical property results are presented for high quality beryllium materials subjected to low-temperature, low-dose neutron irradiation in water-moderated reactors. Materials chosen were the S-65C ITER candidate material produced by Brush Wellman, Kawecki Berylco Industries P0 beryllium, and a high-purity zone refined beryllium. Mini-sheet tensile and thermal diffusivity specimens were irradiated in the temperature range of ∼100–300 °C with a fast (E>0.1 MeV) neutron fluence of 0.05–1.0×1025n/m2in the high flux isotope reactor (HFIR) at the Oak Ridge National Laboratory and the high flux beam reactor (HFBR) at the Brookhaven National Laboratory. As expected from earlier work on beryllium, both materials underwent significant tensile embrittlement with corresponding reduction in ductility and increased strength. Both thermal diffusivity and volumetric expansion were measured and found to have negligible changes in this temperature and fluence range. Of significance from this work is that while both materials rapidly embrittle at these ITER relevant irradiation conditions, some ductility (1–2%) remains, which contrasts with a body of earlier work including recent work on the Brush-Wellman S-65C material irradiated to slightly higher neutron fluence.