Prediction of the Shift in the Brittle-Ductile Transition Temperature of Light-Water Reactor (LWR) Pressure Vessel Materials
- 1 July 1983
- journal article
- Published by ASTM International in Journal of Testing and Evaluation
- Vol. 11 (4) , 237-260
- https://doi.org/10.1520/jte10288j
Abstract
No abstract availableThis publication has 3 references indexed in Scilit:
- Further Observations on A533-B Steel Plate Tailored for Improved Radiation Embrittlement ResistanceJournal of Pressure Vessel Technology, 1976
- Mechanical property and neutron spectral analyses of the big rock point reactor pressure vesselNuclear Engineering and Design, 1970
- Neutron radiation embrittlement of lacrosse reactor pressure vessel steel and weldment: Properties and directionality considerationsNuclear Engineering and Design, 1968