Residual stress behavior in fast neutron irradiated SA AISI 304l stainless steel cylindrical tubing
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Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals
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References (11)
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1. Flinn · 1976 · 253
2. J.E. Flinn, R.A. Weiner and G.L. Hofman, Fast Neutron Swelling of Type 304 Stainless Steels with Special Reference to Type 304L (authors' unpublished data).
3. Walters · 1977 · 277
4. J.E. Flinn and W.G. Wolfer, Stress Effect Consideration for the Enhanced Swelling of Type 304L Stainless Steel Fueled Cladding (authors' unpublished data).
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6. Foster · Nucl. Eng. Design · 1974 · 31 · 11710.1016/0029-5493(74)90141-1 ↗
7. Foster · J. Nucl. Mater. · 1975 · 55 · 11910.1016/0022-3115(75)90145-2 ↗
8. Theory of Inelastic Structures
9. Straalsund · Nucl. Technol. · 1973 · 20 · 2710.13182/NT73-2 ↗
10. Garner · 1976 · 208
11. Nuclear System Materials Handbook (Hanford Engineering Development Laboratory, Richland, WA).