STP1270

    Modeling of Irradiation Embrittlement and Annealing/Recovery in Pressure Vessel Steels

    Published: Jan 1996


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    Abstract

    The results of reactor pressure vessel (RPV) annealing studies are interpreted in light of the current understanding of radiation embrittlement phenomena in RPV steels. An extensive RPV irradiation embrittlement and annealing database has been compiled and the data reveal that the majority of annealing studies completed to date have employed test reactor irradiated weldments. Although test reactor and power reactor irradiations result in similar embrittlement trends, subtle differences between these two damage states can become important in the interpretation of annealing results. Microstructural studies of irradiated steels suggest that there are several different irradiation-induced microstructural features that contribute to embrittlement. The amount of annealing recovery and the post-anneal re-embrittlement behavior of a steel are determined by the annealing response of these microstructural defects. The active embrittlement mechanisms are determined largely by the irradiation temperature and the material composition. Interpretation and thorough understanding of annealing results require a model that considers the underlying physical mechanisms of embrittlement. This paper presents a framework for the construction of a physically based mechanistic model of irradiation embrittlement and annealing behavior.

    Keywords:

    pressure vessel steel, irradiation, embrittlement, annealing, recovery, models, microstructure, mechanisms, coarsening, microhardness, precipitates


    Author Information:

    Lott, RG
    Senior engineer/scientist and engineer/scientist, Westinghouse Science and Technology Center, Pittsburgh, PA

    Freyer, PD
    Senior engineer/scientist and engineer/scientist, Westinghouse Science and Technology Center, Pittsburgh, PA


    Paper ID: STP16469S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP16469S


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