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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Post-irradiation annealing behavior of microstructure and hardening of a reactor pressure vessel steel studied by positron annihilation and atom probe tomography
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Post-irradiation annealing behavior of microstructure and hardening of a reactor pressure vessel steel studied by positron annihilation and atom probe tomography

机译:用正电子an没和原子探针层析成像技术研究反应堆压力容器钢的辐照后退火行为和硬化

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Post-irradiation annealing (PIA) behavior of irradiation-induced microstructural changes and hardening of an A533B (0.16 wt.% Cu) steel after neutron-irradiation of 3.9 × 10 ~(19) n 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.
机译:辐照后中子辐照3.9×10〜(19)n cm〜(-2)(0.061每通过正电子an没光谱法(PAS),原子探针层析成像(APT)和维氏显微硬度测量研究了290°C的原子(dpa)。巧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)以辐照状态进行450℃的退火和(ii)450到600℃的退火。第一阶段是由于大多数与辐射有关的与空位有关的缺陷中的退火所致,而第二阶段则对应于由辐射引起的溶质纳米团簇(SCs)的溶解。 APT观察表明,SC富含Cu,Mn,Ni和Si,并且其数量密度随退火温度的升高而降低,而不会变粗,从而在550°C时几乎完全恢复。实验硬化几乎是Russell-Brown模型在350°C以下估计的SC硬化的两倍,而与在400-550°C范围内估计的SC硬化几乎相同。

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