The response of austenitic steels to radiation damage
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OpenAlex topics: Fatigue and fracture mechanics · Microstructure and Mechanical Properties of Steels · Fusion materials and technologies
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References (31)
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1. Relationship Between Phase Development and Swelling of AISI 316 During Temperature Changes
2. Swelling Behavior of 20% CW 316 Stainless Steel Cladding Irradiated with and Without Adjacent Fuel
3. Recent Experimental and Theoretical Insights on the Swelling of Austenitic Alloys
4. Microstructural and Microchemical Comparisons of AISI 316 Irradiated in HFIR and EBR-II10.1016/0022-3115(83)90022-3 ↗
5. F.A. Garner, “Recent Insights on the Swelling and Creep of Irradiated Austenitic Alloys,” this volume.
6. Radiation-Induced Swelling in an Austenitic Alloy: Observations and Interpretation of the Effects of Helium10.13182/FST83-A20863 ↗
7. Fission-Fusion Correlations for Swelling and Microstructure in Stainless Steels: Effect of the Helium to Displacement per Atom Ratio10.1016/0022-3115(82)90779-6 ↗
8. Advances in the Theory of Swelling in Irradiated Metals and Alloys10.1016/0022-3115(79)90541-5 ↗
9. The Effect of Phase Instabilities on the Correlation of Nickel Ion and Neutron Irradiation Swelling in S.A. 316 Stainless Steel
10. P.J. Maziasz, “Swelling and Swelling Resistance Possibilities of Austenitic Stainless Steels in Fusion Reactors,” this volume.
11. The Effect of Helium on Swelling in Stainless Steel: Influence of Cavity Density and Morphology
12. Materials Development for Fast Breeder Reactor Cores10.13182/NT82-A26308 ↗
13. R.A. Weiner and A. Boltax, “Comparison of High Fluence Swelling Behavior of Austenitic Stainless Steels,” p. 484–499 in: Proc. 10th Symp. on Effects of Radiation on Materials, Savannah, GA, ASTM-STP-725.10.1520/STP28231S ↗
14. High Temperature Radiation Damage Phenomena in Complex Alloys10.1016/0022-3115(82)90500-1 ↗
15. Effects of Pulsed Dual-Ion Irradiation on Phase Transformations and Microstructrure in Ti-Modified Austenitic Alloy10.1016/0022-3115(83)90018-1 ↗
16. Mechanisms of Helium Interaction with Radiation Effects in Metals and Alloys: A Review
17. E.H. Lee, L.K. Mansur, and A.F. Rowcliffe, “The Effect of Phosphorus on the Swelling and Precipitation Behavior of Austenitic Stainless Steels During Irradiation,” this volume.
18. Flow and Fracture of Alloys in the Fusion Environment10.1016/0022-3115(82)90780-2 ↗
19. A Microstructural Interpretation of the Fluence and Temperature Dependence of the Mechanical Properties of Irradiated AISI 316
20. The Effects of Large Concentrations of Helium on the Mechanical Properties of Neutron-Irradiated Stainless Steels10.1016/0022-3115(75)90103-8 ↗
21. Tensile Properties and Swelling of 20%-Co Id-Worked Type 316 Stainless Steel Irradiated in HFIR
22. Some Effects of Increased Helium Content on Void Formation and Solute Segregation in Neutron-Irradiated Type 316 Stainless Steel10.1016/0022-3115(82)90505-0 ↗
23. An In-Reactor Creep Correlation for 20% CW AISI 316 Stainless Steel
24. The Effects of Temperature and Dose-Rate Variations on the Creep of Austenitic Stainless Steels in the Dounreay Fast Reactor10.1016/0022-3115(80)90257-3 ↗
25. The Irradiation Creep of Nickel and AISI 321 Stainless Steel During 4 MeV Proton Bombardment10.1016/0022-3115(77)90066-6 ↗
26. Fatigue Behavior of Type 316 Stainless Steel Irradiated in a Mixed Spectrum Fission Reactor Forming Helium10.13182/NT82-A32987 ↗
27. High-Temperature Fatigue Life of Type 316 Stainless Steel Containing Irradiation Induced Helium10.1016/0022-3115(82)90706-1 ↗
28. The Influence of Helium on High Temperature Fatigue of Type 316 Stainless Steel
29. Fatigue Life at 650°C of 20%-Cold-Worked Type 316 Stainless Steel Irradiated in the HFIR at 550°C
30. Irradiation Embrittlement of Type 304 Stainless Steel Welds and Plate at 823 K (550°C)
31. Deformation Microstructure Developed During Fatigue Crack Propagation in Type 316 Stainless Steel at 593°C