Tensile properties of type 316 stainless steel irradiated in a simulated fusion reactor environment
Bibliographic record
Abstract
No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.
Source: Not provided · Quality: missing
Research context
OpenAlex topics: Fusion materials and technologies · Microstructure and Mechanical Properties of Steels · Hydrogen embrittlement and corrosion behaviors in metals
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (9)
Show source-provided references
1. Swelling, Mechanical Properties and Microstructure of Type 316 Stainless Steel at Fusion Reactor Damage Levels
2. Weitman · Trans. Am. Nucl. Soc. · 1970 · 13 · 557
3. Bloom · J. Nucl. Mater. · 1975 · 58 · 17110.1016/0022-3115(75)90103-8 ↗
4. The Effects of CTR Irradiation on the Mechanical Properties of Structural Materials
5. F. W. Wiffen et al., The Production Rate of Helium During Irradiation of Nickel in Thermal Spectrum Fission Reactors, this conference.
6. Analysis of Stress-Strain Behavior of Type 316 Stainless Steel
7. Fish · 1976 · 91
8. Fish · 1976 · 119
9. P. J. Maziasz, Oak Ridge National Laboratory, private communication, 1979.