1. Positron Annihilation Study of Neutron-Irradiated Nuclear Reactor Pressure Vessel Steels and their Model Alloy: Effect of Purity on the Post-Irradiation Annealing Behavior
- Author
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Yasuyoshi Nagai, Takeshi Toyama, Akira Kuramoto, Minoru Hasegawa, and Tomoaki Takeuchi
- Subjects
Materials science ,Annealing (metallurgy) ,Mechanical Engineering ,Alloy ,Metallurgy ,Analytical chemistry ,Atom probe ,engineering.material ,Condensed Matter Physics ,Indentation hardness ,Positron annihilation spectroscopy ,law.invention ,Mechanics of Materials ,law ,Hardening (metallurgy) ,engineering ,General Materials Science ,Neutron ,Irradiation - Abstract
Post-irradiation annealing (PIA) behavior of irradiation-induced microstructural changes and hardening of two kind of A533B (first generation (1stGENS: 0.16 wt.% Cu) and second generation (2ndGENS: 0.04 wt.% Cu)) steels after neutron-irradiation of 3.9 × 1019 n cm–2 at 290 °C has been studied by positron annihilation spectroscopy, atom probe tomography and Vickers microhardness measurements. In the 1stGENS, clear two recovery stages are observed: (i) as-irradiated state to 450 °C and (ii) 450 to 600 °C. The first stage is due to annealing out of the most of irradiation-induced vacancy-related defects (VRDs), and the second stage corresponds to dissolving irradiation-induced Cu-rich solute nano-clusters (CRSCs). The experimental hardening is almost twice of the hardening due to the CRSCs estimated by Russell-Brown model below 350 °C, but almost the same as the estimation from 400 to 550 °C. In the 2ndGENS, the VRDs and non-Cu-rich solute nano-clusters (NCRSCs) recover at 450 °C. No CRSC has been formed even in all the annealing process. The experimental hardening is almost twice of the hardening estimated due to the NCRSCs by Russell-Brown model below 400 °C.
- Published
- 2012