首页> 外文会议>International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors >FABRICATION-INDUCED WELD RESIDUAL STRESSES IN AUSTENITIC STAINLESS STEEL DRY CASK STORAGE SYSTEM CANISTERS SUSCEPTIBLE TO CHLORIDE-INDUCED STRESS CORROSION CRACKING
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FABRICATION-INDUCED WELD RESIDUAL STRESSES IN AUSTENITIC STAINLESS STEEL DRY CASK STORAGE SYSTEM CANISTERS SUSCEPTIBLE TO CHLORIDE-INDUCED STRESS CORROSION CRACKING

机译:奥氏体不锈钢干燥桶储存系统罐易受氯化物诱导的应力腐蚀开裂的制造诱导的焊接残余应力

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Several in-service Dry Cask Storage System (DCSS) designs in the United States utilize an austenitic stainless steel canister to confine spent nuclear fuel (SNF). These canisters are stored within concrete shielding structures that have vents which allow for convective cooling and, consequently, expose the canister surface to any chlorides present in the atmosphere. Chloride salts that deposit on the canister surface can deliquesce in specific environments, resulting in the aqueous solution necessary to initiate chloride-induced stress corrosion cracking (SCC) if tensile stresses are present. While tensile stresses are thought to be present on the canister surface due to forming and welding operations, the magnitude of these stresses has not been quantified. This paper documents the results of a sequentially coupled thermal-structural finite element analysis for a generic canister configuration, including a discussion of analytical methods, assumptions, potential implications, uncertainties, and further potential research areas.
机译:美国的几种在职干桶储存系统(DCS)设计利用奥氏体不锈钢罐来限制核燃料(SNF)。这些罐储存在混凝土屏蔽结构内,该结构具有允许对流冷却的通风口,因此将罐表面暴露于大气中存在的任何氯化物。如果存在拉伸应力,则沉积在罐表面上的氯化物盐可以在特定环境中脱发,导致氯化物诱导的应力腐蚀裂化(SCC)所需的水溶液。虽然由于成形和焊接操作而被认为存在拉伸应力存在于罐表面上,但是这些应力的大小尚未被定量。本文记录了通用罐配置的顺序耦合的热结构有限元分析结果,包括讨论分析方法,假设,潜在影响,不确定性和进一步的潜在研究区域。

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