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Microstructure of the Neutron Irradiated VVER-type Reactor Pressure Vessel Steels

机译:中子辐照vver型反应器压力容器钢的微观结构

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Conventional transmission electron microscopy has been used to investigate the radiation-induced changes in the microstructure of VVER-type RPV steels. Specimens irradiated at approx approx 270deg C temperature in both the power light-water reactor (surveillance specimens) and the research reactor have been studied. In addition, the microstructure of the thermally aged specimens was analyzed too. Microstructural analysis has been supplemented by some preliminary results of the Dopler broadenign and lifetime positron annihilation measurements. Radiation-induced matrix defects visible by TEM in power reactor surveillance specimens consist of black dots, small dislocation loops and fine precipitates distributed heterogeneously with a dislocation substructure. Evolution of the radiation damage structure depends on the neutron fluence and the neutron flux. Only hardly discernible black dots were observed in specimens irradiated in the research reactor in NRI Rez. However, also in this case, the presence of a vacancy-rich component in the damage structure was suggested by positron lifetime measurements.
机译:常规的透射电子显微镜已经用于研究Vver型RPV钢的微观结构的辐射诱导的变化。研究了在电力 - 反应器(监测标本)中大约约270deg C温度下照射的试样和研究反应器。另外,分析了热老化样本的微观结构。通过多普勒广播和终身正电子湮没测量的一些初步结果,已经补充了微观结构分析。辐射诱导的基质缺陷在功率反应器监测样本中可见的TEM由黑点组成,小脱位环和细沉淀物与错位子结构分布。辐射损伤结构的演变取决于中子流量和中子通量。在NRI Rez的研究反应器中辐照的标本中仅观察到几乎不可辨别的黑点。然而,在这种情况下,通过正电子寿命测量提出了损伤结构中富含空位的富含空位的组分。

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