In support of evaluating long-term operationalperformance of materials used in core internalcomponents, the Oak Ridge National Laboratory (ORNL),through the U.S. Department of Energy (DOE) LightWater Reactor Sustainability (LWRS) Program, hasobtained specimens machined from two high fluencebaffle-former bolts (BFBs) retrieved from a Westinghousetwo-loop downflow type pressurized water reactor(PWR). The bolt material is type 347 austenitic stainlesssteel and the calculated irradiation damage levels rangefrom 15 to 41 displacements per atom. Electronmicroscopy characterization was performed on one of thetwo retrieved BFBs to evaluate radiation-induceddamages, such as dislocation loops, cavities, segregation,precipitation, etc. Results from this study should fill thecurrent knowledge gap in radiation-inducedmicrostructural changes for type 347 austenitic stainlesssteels (SS) after high fluence PWR irradiation.
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