Estimates of Time-Dependent Fatigue Behavior of Type 316 Stainless Steel Subject to Irradiation Damage in Fast Breeder and Fusion Power Reactor Systems
- 1 January 1979
- book chapter
- Published by ASTM International
- p. 490-510
- https://doi.org/10.1520/stp38184s
Abstract
No abstract availableKeywords
This publication has 9 references indexed in Scilit:
- Isochronous Relaxation Curves for Type 304 Stainless Steel After Monotonic and Cyclic StrainJournal of Testing and Evaluation, 1979
- ORNL Fusion Power Demonstration Study: Fluid Flow, Heat Transfer, and Stress Analysis Considerations in the Design of Blankets for Full-Scale Fusion Reactors.Published by Office of Scientific and Technical Information (OSTI) ,1978
- The Establishment of Alloy Development Goals Important to the Commercialization of Tokamak-Based Fusion ReactorsPublished by Office of Scientific and Technical Information (OSTI) ,1977
- Calculated irradiation response of materials using a fusion-reactor first-wall neutron spectrumPublished by Office of Scientific and Technical Information (OSTI) ,1977
- Application of Strainrange Partitioning to the Prediction of Creep-Fatigue Lives of AISI Types 304 and 316 Stainless SteelJournal of Pressure Vessel Technology, 1977
- The effects of large concentrations of helium on the mechanical properties of neutron-irradiated stainless steelJournal of Nuclear Materials, 1975
- Low cycle fatigue and hold time comparisons of irradiated and unirradiated type 316 stainless steelMetallurgical Transactions, 1974
- Estimates of Creep-Fatigue Interaction in Irradiated and Unirradiated Austenitic Stainless SteelsNuclear Technology, 1972
- Radiation‐induced point defect clusters in copper and goldPhysica Status Solidi (b), 1966