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Irradiation Assisted Stress Corrosion Cracking (IASCC)

机译:辐照辅助应力腐蚀裂纹(IASCC)

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Irradiation assisted stress corrosion cracking (IASCC) is a potential failure mode suffered by the core-components of austenitic stainless steels in the aged light-water reactor (LWR), which is the intergranular type cracking caused by synergistic effects of neutron/gamma radiation and chemical environment. Effects of radiation on the materials and high-temperature water are discussed in this paper to understand IASCC phenomenon from a mechanistic viewpoint. It is essential to elucidate the radiation-induced micro-compositional and microstructural changes in the alloy for mechanistic and predictive investigations of IASCC. Although grain boundary segregations of alloying and impurity elements are significant factors affecting IASCC, it has been considered that the radiation-induced microstructural and mechanical changes of materials play critical roles in IASCC. For mechanistic understanding of IASCC, further fundamental research works with experimental and theoretical approaches are needed. Efforts directed to the researches at the Japan Atomic Energy Research Institute are also described.
机译:照射辅助应力腐蚀裂纹(IASCC)是由老化的光 - 水反应器(LWR)中奥氏体不锈钢核心组分患病的潜在故障模式,其是中子/γ辐射的协同效应引起的骨间裂纹化学环境。本文讨论了辐射对材料和高温水的影响,以了解机械观点的IASCC现象。必须阐明辐射诱导的合金的微型组合物和微观结构变化,以获得IASCC的机械和预测性研究。尽管合金化和杂质元素的晶粒边界分离是影响IASCC的重要因素,但是被认为是辐射诱导的材料的微观结构和机械变化在IASCC中起重要作用。对于IASCC的机械理解,需要采用实验和理论方法的进一步基础研究。还描述了针对日本原子能研究院研究的努力。

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