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FRACTURE BEHAVIOR OF OXIDIZED GRAIN BOUNDARY IN NEUTRON-IRRADIATED STAINLESS STEEL

机译:中子辐照不锈钢中氧化晶粒边界的断裂行为

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Effects of oxidation on cohesive strength of a grainboundary (GB) was investigated by micro-tensile testingfor stainless steel specimen neutron-irradiated to 73 dpaand then immersed in simulated PWR primary water at320°C. The micro-specimens were fabricated with anoxidized GB and a non-oxidized GB (as-irradiated). Thespecimen with the oxidized GB failed at 1100 Mpa,whereas the specimen with the non-oxidized GB failed at2600 Mpa. It was found that GB oxidation woulddecreased the cohesive strength to one third that of theas-irradiated GB. By considering the stress concentrationon GBs due to deformation constraint in a polycrystallinematerial and dislocation channeling deformation, it wassuggested that the oxidized GBs would crack when thetensile stress was applied on the neutron-irradiatedstainless steel used in high temperature water at the samelevel as the initiation threshold stress of the irradiationassistedstress corrosion cracking (IASCC). Intergranularcracking propagation by repetition of further GBoxidation and its fracture was thought to be one of theinitiation mechanisms of IASCC.
机译:氧化对晶粒内聚强度的影响 边界(GB)通过微拉伸试验研究 用于中子辐照至73 dpa的不锈钢试样 然后浸入模拟的PWR初级水中 320℃。显微样品是用 氧化的GB和未氧化的GB(经辐照)。这 氧化的GB的样品在1100 Mpa时失效, 而未氧化GB的标本在 2600 Mpa。发现GB氧化会 降低了内聚力的三分之一 辐照GB。通过考虑应力集中 多晶中由于变形限制而导致的GBs的变化 物质和位错的通道变形,这是 提示氧化的GBs会在开裂时破裂。 向中子辐照施加拉应力 同时用于高温水中的不锈钢 水平作为辐照辅助的初始阈值应力 应力腐蚀开裂(IASCC)。晶间 重复GB扩展裂纹扩展 氧化及其断裂被认为是其中之一 IASCC的启动机制。

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