In-reactor oxidation of crevices and cracks in cold-worked Zr-2.5 wt% Nb
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Abstract
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Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear Engineering Thermal-Hydraulics
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References (11)
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1. Ross-Ross · Atomic Energy of Canada Limited, Report AECL-5261 · 1976
2. Susceptibility of zirconium alloys to delayed hydrogen cracking
3. On the factors controlling hydrogen assisted sub-critical crack growth in Zr-2.5 wt% Nb
4. Urbanic · Corrosion · 1975 · 13 · 1510.5006/0010-9312-31.1.15 ↗
5. LeSurf · ASTM STP · 1972 · 458 · 286
6. Cox · 1976 · Vol. 5
7. Cox · Atomic Energy of Canada Limited, Report AECL-5610 · 1976
8. Larrick · Battelle Northwest Laboratory Report BNWL-CC-14-1 · 1967
9. Coriou · J. Nucl. Mater. · 1962 · 7 · 32010.1016/0022-3115(62)90249-0 ↗
10. Hillner · Bettis Atomic Power Laboratory Report, WAPD-TM-307 · 1962
11. Murgatroyd · J. Nucl. Mater. · 1967 · 23 · 24910.1016/0022-3115(67)90157-2 ↗