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Title: Low Temperature Irradiation Embrittlement of Reactor Pressure Vessel Steels

The embrittlement trend curve development project for HFIR reactor pressure vessel (RPV) steels was carried out with three major tasks. Which are (1) data collection to match that used in HFIR steel embrittlement trend published in 1994 Journal Nuclear Material by Remec et. al, (2) new embrittlement data of A212B steel that are not included in earlier HFIR RPV trend curve, and (3) the adjustment of nil-ductility-transition temperature (NDTT) shift data with the consideration of the irradiation temperature effect. An updated HFIR RPV steel embrittlement trend curve was developed, as described below. NDTT( C) = 23.85 log(x) + 203.3 log (x) + 434.7, with 2- uncertainty of 34.6 C, where parameter x is referred to total dpa. The developed update HFIR RPV embrittlement trend curve has higher embrittlement rate compared to that of the trend curve developed in 1994.
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
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Resource Type:
Technical Report
Research Org:
Oak Ridge National Laboratory (ORNL), High Flux Isotope Reactor (HFIR)
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Country of Publication:
United States
embrittlement trend; nil-ductility-transition temperature; total dpa; radiation embrittlement; reactor pressure vessel steel