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Mechanical Properties of Thermally Aged Cast Stainless Steels from Shippingport Reactor Components

机译:船舶反应器部件热老化不锈钢的力学性能

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Thermal embrittlement of static-cast CF-8 stainless steel components from the decommissioned Shippingport reactor has been characterized. Cast stainless steel materials were obtained from four cold-leg check valves, three hot-leg main shutoff valves, and two pump volutes. Baseline mechanical properties for as-cast material were determined from tests on either recovery-annealed material or material from the cooler region of the component. The Shippingport materials show modest decreases in fracture toughness and Charpy-impact properties and a small increase in tensile strength because of relatively low service temperatures and ferrite content of the steel. The procedure and correlations developed at Argonne National Laboratory for estimating mechanical properties of cast stainless steels predict accurate or slightly lower values for Charpy-impact energy, tensile flow stress, fracture toughness J-R curve, and JIC of the materials. The kinetics of thermal embrittlement and degree of embrittlement at saturation were established from materials that were aged further in the laboratory. The results were consistent with the estimates.

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