Irradiation growth in zirconium-tin alloys at 353 and 553 K
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OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
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References (12)
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1. Zee · J. Nucl. Mater. · 1984 · 120 · 22410.1016/0022-3115(84)90060-6 ↗
2. Zirconium in the Nuclear Industry: Sixth Int. Symp.
3. Rogerson · J. Nucl. Mater. · 1983 · 113 · 25610.1016/0022-3115(83)90151-4 ↗
4. A. Rogerson. Irradiation growth in annealed and 25% cold-worked Zircaloy-2 between 353 and 673 K, submitted to J. Nucl. Mater.10.1016/0022-3115(88)90364-9 ↗
5. Holt · J. Nucl. Mater. · 1986 · 137 · 18510.1016/0022-3115(86)90218-7 ↗
6. Irradiation growth in zirconium and its alloys
7. Microstructure evolution in zirconium alloys during irradiation
8. Characterisation of the dislocation network in post-irradiation annealed Zircaloy-2
9. Some observations on the role of irradiation-induced microstructure in irradiation growth ‘breakaway’ in Zircaloy-4
10. High fluence irradiation growth of zirconium alloys at 644 and 725 K
11. Bullough · J. Nucl. Mater. · 1980 · 90 · 110.1016/0022-3115(80)90241-X ↗
12. Hood · J. Nucl. Mater. · 1984 · 126 · 7910.1016/0022-3115(84)90536-1 ↗