Tensile Properties of Irradiated Pressure Vessel Steels
- 1 January 1987
- book chapter
- Published by ASTM International
- p. 379-394
- https://doi.org/10.1520/stp25663s
Abstract
Yield stress and hardness changes have been demonstrated to be strongly correlated to transition temperature shifts in nuclear pressure vessel steels, and hence such measurements can be a convenient means for evaluating the role of metallurgical and environmental variables in embrittlement. We have irradiated miniature tensile specimens of over 100 alloy (chemistry and thermomechanical treatment) variants at nominal fluxes 0.5 to 5 × 1016 n/m2·s, temperatures 271 to 325°C, and fluences 0.15 to 3 × 1023 n/m2. A subset of these specimens has been tested, and the results are reported here. For both commercial and model alloys, good agreement between hardness and yield stress changes were observed. Yield stress changes were strongly influenced by copper and nickel content and by thermomechanical treatment.Keywords
This publication has 7 references indexed in Scilit:
- Irradiation Embrittlement of Reactor Pressure Vessel Steels: Mechanisms, Models, and Data CorrelationsPublished by ASTM International ,1986
- Microanalytical Studies of Pressure Vessel Weld MaterialsPublished by ASTM International ,1986
- Effects of Composition, Microstructure, and Temperature on Irradiation Hardening of Pressure Vessel SteelsPublished by ASTM International ,1985
- Relationship Between Irradiation Hardening and Embrittlement of Pressure Vessel SteelsPublished by ASTM International ,1985
- Neutron source characterization for fusion materials studiesJournal of Nuclear Materials, 1981
- Thermodynamic analysis of solubility and miscibility gap in ferromagnetic alpha iron alloysActa Metallurgica, 1979
- The determination of yield strength from hardness measurementsMetallurgical Transactions, 1971