An investigation of thermal release of carbon-14 from PWR Zircaloy spent fuel cladding
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Abstract
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Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear and radioactivity studies
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References (13)
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1. 10 CFR 60
2. Van Konynenburg · Scientific Basis for Nuclear Waste Management, MRS · 1987 · vol. 84 · 185
3. Potential Corrosion and Degradation Mechanisms of Zircaloy Cladding on Spent Nuclear Fuel in a Tuff Repository
4. Godlewski · 1991 · 1132 · 416
5. Guenther · 1990
6. The Mathematics of Diffusion
7. Agarwala · J. Nucl. Mater. · 1975 · 58 · 2510.1016/0022-3115(75)90162-2 ↗
8. Zotov · Phys. Met. Metall. · 1980 · 47 · 103
9. Kopp · J. Nucl. Mater. · 1990 · 173 · 110.1016/0022-3115(90)90306-8 ↗
10. Van Konynenburg · Scientific Basis for Nuclear Waste Management, MRS · 1985 · vol. 44 · 405
11. 1986
12. 1987
13. 1987