Container materials in environments of corroded spent nuclear fuel
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Abstract
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Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Nuclear Materials and Properties · Graphite, nuclear technology, radiation studies
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References (19)
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6. Ballinger · 1994
7. Dry Storage of N Reactor Fuel Independent Technical Assessment
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9. Assessment of Delayed Failure Models in Titanium and Titanium Alloys
10. M.R. Louthan, in: Hydrogen in Metals, ed. I.M. Bernsteil and A.W. Thompson (ASM, Metals Park, OH) p. 53.
11. Liu · Metall. Trans. · 1980 · 11A · 156310.1007/BF02654520 ↗
12. Fracture Properties of Irradiated Alloys
13. Anderson · 1989 · I-83
14. Clarke · 1983 · 451
15. Clarke · 1985 · 442
16. Fujita · Corrosion · 1981 · 37 · 33510.5006/1.3577282 ↗
17. Long-Term Performance of Container Materials for High- Level Waste
18. Bachelay · 1986
19. 1989