Fatigue crack growth behaviour of A533B steel in simulated pwr water
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Research context
OpenAlex topics: Fatigue and fracture mechanics · Material Properties and Failure Mechanisms · Non-Destructive Testing Techniques
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References (18)
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1. Corrosion fatigue of ASTM A-302B steel in high temperature water, in simulated nuclear reactor environment
2. The effect of frequency and environment on the fatigue-crack growth behaviour of ASTM A533B weldment material10.1016/0142-1123(79)90004-5 ↗
3. Fatigue crack growth in X-65 line-pipe steel at low cyclic frequencies in aqueous environments
4. ASME Boiler and Pressure Vessel Code, Section XI, App. A, In Service Inspection of Nuclear Power Plant Components (1974 Edition).
5. The Influence of Environment on Fatigue
6. Yvzawich · Pract. Metall. · 1978 · 15 · 18410.1515/pm-1978-150404 ↗
7. Atkinson · Metal Sci. · 1979 · 7 · 44410.1179/msc.1979.13.7.444 ↗
8. Fatigue crack growth of A508 steel in high temperature, pressurised reactor grade water
9. Bamford · Corrosion · 1980 · 6 · 28910.5006/0010-9312-36.6.289 ↗
10. Ford · 1980 · Vol. 2 · 431
11. Scott · 1981 · 109
12. Torrenen · 1981 · 313
13. A fractographic study of the effects of varying dissolved oxygen level on the cyclic crack growth of A533B steel in high temperature reactor grade water
14. Fatigue crack propagation in A533B steels10.1115/1.3454560 ↗
15. Environmentally assisted crack growth in light water reactor materials
16. Environmentally assisted crack growth in light water reactor materials
17. Elber · ASTM STP · 1971 · 486 · 230
18. Stewart · Eng. Fracture Mech. · 1980 · 13 · 46310.1016/0013-7944(80)90078-8 ↗