Iodine stress corrosion cracking of zircaloy: Laboratory data, a phenomenological model, and predictions of in-reactor behavior
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OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
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References (15)
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1. Jones · J. Nucl. Mater. · 1979 · 82 · 2610.1016/0022-3115(79)90036-9 ↗
2. WAPD-TM-1248
3. Peehs · 1979 · 681 · 244
4. EPRI NP-1329
5. EPRI NP-1557
6. Syrett · J. Nucl. Mater. · 1980 · 92 · 8910.1016/0022-3115(80)90145-2 ↗
7. Kreyns · J. Nucl. Mater. · 1976 · 61 · 20310.1016/0022-3115(76)90084-2 ↗
8. EPRI NP-1798
9. Ph.D. dissertation
10. Bain · LRC 4733-7 · 1979
11. Stress and strain at Zircaloy cladding ridges
12. Cox · 1977 · 520
13. Woodford · J. Eng. Mater. Technol. · 1979 · 101 · 31110.1115/1.3443695 ↗
14. Penn · Nucl. Technol. · 1977 · 34 · 249
15. The influence of environmental variables and irradiation on stress corrosion crack initiation and growth in Zircaloy