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Irradiation damage in nuclear reactor steels/ a comprehensive approach of the solute cluster formation using ion irradiation simulations for the defect production

机译:核反应堆钢的辐照损伤/使用离子辐照模拟进行溶质簇形成的综合方法,用于缺陷生产

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Vessel and internal core steels of nuclear power reactors are subjected to energetic neutron irradiation. The production of point defects in the material results from elastic collisions in displacement cascades. At a microscopic scale, changes in the microstructure and local microchemistry are observed in both steels. At the global scale, a shift in the transient ductile to brittle temperature of vessel steels is observed, as well as an increase in the Irradiated Assisted Stress Corrosion Cracking (IASCC) susceptibility (and global strength/hardening of the material) of internal core stainless steels. Also, at the nanometric scale, radiation induced phase transformation occurs in both steels.
机译:核电力反应堆的血管和内核钢进行了能量中子辐照。材料中的点缺陷的产生是由位移级联的弹性碰撞产生的。在显微尺度下,在两个钢中观察到微观结构和局部微化的变化。在全球范围内,观察到瞬态延展性的瞬态延展性转变为血管钢的脆性温度,以及辐照辅助应力腐蚀裂纹(IASCC)易感性(和材料的全球强度/硬化)的增加的内核不锈钢钢。而且,在纳米级,在两个钢中发生辐射诱导的相变。

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