Post-irradiation annealing behavior of microstructure and hardening of a reactor pressure vessel steel studied by positron annihilation and atom probe tomography

Post-irradiation annealing behavior of microstructure and hardening of a reactor pressure vessel steel studied by positron annihilation and atom probe tomography
复制标题

DOI:
10.1016/j.jnucmat.2011.10.019
复制
发表时间:
2012-06
影响因子:
3.1
通讯作者:
A. Kuramoto;T. Toyama;T. Takeuchi;Y. Nagai;M. Hasegawa;T. Yoshiie;Y. Nishiyama
A. Kuramoto;T. Toyama;T. Takeuchi;Y. Nagai;M. Hasegawa;T. Yoshiie;Y. Nishiyama
中科院分区:
工程技术2区
文献类型:
--
作者:
A. Kuramoto;T. Toyama;T. Takeuchi;Y. Nagai;M. Hasegawa;T. Yoshiie;Y. Nishiyama

文献摘要

相似文献

通过正电子湮没能谱 (PAS)、原子探针断层扫描 (APT) 和维氏硬度研究了 A533B (0.16wt.% Cu) 钢在 290°C 下 3.9×1019n cm−2(每个原子位移 (dpa) 0.061)中子辐照后的辐照后退火 (PIA) 行为。显微硬度测量。重合多普勒展宽和正电子寿命测量清楚地揭示了两个恢复阶段; (i) 辐照状态至 450°C 退火,以及 (ii) 从 450°C 退火至 600°C。第一阶段是由于退火消除了大多数辐照引起的空位相关缺陷,而第二阶段对应于辐照引起的溶质纳米团簇(SC)的溶解。 APT 观察结果表明,SC 富含 Cu、Mn、Ni 和 Si,并且它们的数密度随着退火温度的升高而降低,而没有粗化,在 550°C 时几乎完全恢复。在 350°C 以下,实验硬化几乎是 Russell-Brown 模型估计的 SC 硬化的两倍,而在 400-550°C 范围内几乎与估计的相同。
Post-irradiation annealing (PIA) behavior of irradiation-induced microstructural changes and hardening of an A533B (0.16wt.% Cu) steel after neutron-irradiation of 3.9×1019n cm−2(0.061 displacement per atom (dpa)) at 290°C was studied by positron annihilation spectroscopy (PAS), atom probe tomography (APT) and Vickers microhardness measurements. Coincidence Doppler broadening and positron lifetime measurements clearly reveal two recovery stages; (i) as-irradiated state to annealing at 450°C and (ii) annealing from 450 to 600°C. The first stage is due to annealing out of the most of irradiation-induced vacancy-related defects, while the second stage corresponds to dissolving of irradiation-induced solute nanoclusters (SCs). APT observations reveal that the SCs are enriched with Cu, Mn, Ni and Si and that their number densities decrease with increasing annealing temperature without coarsening to give almost complete recovery at 550°C. The experimental hardening is almost twice the SC hardening estimated by the Russell–Brown model below 350°C, whereas it is almost the same as that estimated in the range 400–550°C.