Effects of dissolved oxygen on corrosion fatigue cracking of Alloy 690(TT) in pressurized water reactor environments
Source abstract
Abstract
Abstract Alloy 690(TT) is widely used for steam generator tubes in pressurized water reactor (PWRs), where it is susceptible to corrosion fatigue. In this study, the effects of dissolved oxygen on the corrosion fatigue cracking behavior of Alloy 690(TT) in simulated PWR environments were investigated under small scale yielding conditions. Dissolved oxygen, combined with the monotonic plastic zone size (rp), had a significant influence on out-of-plane cracking of corrosion fatigue crack and environment factor (Fen).
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fatigue and fracture mechanics · Non-Destructive Testing Techniques · Hydrogen embrittlement and corrosion behaviors in metals
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (15)
Show source-provided references
1. Ruther WE, Soppet WK, Kassner TF. Corrosion fatigue of Alloys 600 and 690 in simulated LWR environments. NUREG/CR–6383, ANL–95/37; 1996.10.2172/219363 ↗
2. Ruther WE, Soppet WK, Kassner TF. Environmentally assisted cracking in light water reactors, semiannual report. NUREG/CR–4667, ANL–98/18; July 1997–December 1997 p. 42–75.
3. Ruther WE, Soppet WK, Kassner TF, Shack WJ. Environmentally assisted cracking in light water reactors, semiannual report January 1998–July 1998. NUREG/CR–4667 vol. 26;1999, ANL–98/18. p. 25–32.
4. Ruther WE, Soppet WK, Kassner TF, Shack WJ. Environmentally assisted cracking in light water reactors, semiannual report. July 1998–December 1998. NUREG/CR–4667 vol. 27; 1999, ANL–99/11. p. 45–54.
5. Soppet WK, Chopra OK, Shack WJ. Environmentally assisted cracking in light water reactors, semiannual report. January 1999–June 1999. NUREG/CR–4667 vol. 28; 2000, ANL–00/7. p. 40–41.
6. Soppet WK, Chopra OK, Shack WJ. Environmentally assisted cracking in light water reactors, semiannual report. July 1999–December 1999, NUREG/CR–4667 vol. 29; 2000, ANL–00/23. p. 39–45.
7. Soppet WK, Chopra OK, Shack WJ. Environmentally assisted cracking in light water reactors, semiannual report. January 2000–June 2000. NUREG/CR–4667 vol. 30; 2001, ANL–01/08. p. 49–50.10.2172/925022 ↗
8. Jenssen · 2008
9. The response of alloy 690 tubing in a pressurized water reactor environment10.1016/j.matdes.2005.10.001 ↗
10. An investigation of the fatigue crack growth behavior of INCONEL 69010.1016/j.msea.2005.09.101 ↗
11. Saturation dislocation structures in cyclically deformed nickel single crystal of different orientations10.1002/crat.2170170610 ↗
12. The development of dislocation structures during the fatigue process of F.C.C single crystals10.1002/crat.2170171219 ↗
13. The mechanisms and temperature dependence of supperlattice stacking fault formation in the single-crystal superalloy PWA148010.1007/BF02664997 ↗
14. Crack deflection: implications for growth of long and short fatigue cracks10.1007/BF02663313 ↗
15. Crack deflection