Corrosion fatigue crack growth behavior of alloy 52 M in high-temperature water
Source abstract
Abstract
Abstract The corrosion fatigue (CF) crack growth behavior of Alloy 52 M in high temperature water was investigated in various water chemistries with dissolved oxygen (DO), dissolved hydrogen (DH) or Ar. The experimental results indicated that at higher load ratio (R), the CF crack growth rates (CGRs) in oxygenated water was slightly higher than Ar deaerated water, while under lower R, the relationship was reversed. Micro-characterization of the crack paths and fracture surfaces revealed that severe crack branching and localized inter-dendritic cracking occurred in oxygenated water, while relatively straight transgranular cracking developed in hydrogen and Ar deaerated water. Minor environmental enhancement of CGRs for Alloy 52 M weld metal was detected in oxygenated water but no environmental enhancement of CGRs was detected in hydrogen or Ar deaerated water.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Fatigue and fracture mechanics · High Temperature Alloys and Creep
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (40)
Show source-provided references
1. Stress corrosion cracking of current structural materials in commercial nuclear power plants10.5006/0801 ↗
2. PWSCC of alloys 690, 52 and 152
3. Effects of hydrogen on stress corrosion crack growth rate of nickel alloys in high-temperature water10.5006/1.3278508 ↗
4. Alexandreanu · 2006 · 153
5. Cyclic and SCC behavior of Alloy 690 HAZ in a PWR environment
6. SCC behavior of Alloy 152 weld in a PWR environment
7. Linking grain boundary microstructure to stress corrosion cracking of cold-rolled alloy 690 in pressurized water reactor primary water10.5006/0808 ↗
8. Characterizing the effect of creep on stress corrosion cracking of cold worked Alloy 690 in supercritical water environment10.1016/j.jnucmat.2017.05.018 ↗
9. Corrosion fatigue crack growth behavior of Alloy 690 in high-temperature pressurized water10.5006/2324 ↗
10. Recommended capabilities, best practices and reporting requirements for SCC growth rate testing of resistant materials in PWR primary water, adopted by the Alloy 690/52/152 PWSCC Research Collaboration, K. Ahluwalia (Coordinator)
11. Materials Reliability Program (MRP) · 2004
12. Residual strain measurement and grain boundary characterization in the heat-affected zone of a weld joint between Alloy 690TT and Alloy 5210.1016/j.jnucmat.2009.12.016 ↗
13. An investigation of the fatigue crack growth behavior of INCONEL 69010.1016/j.msea.2005.09.101 ↗
14. Environmentally assisted crack growth in one-dimensionally cold worked Alloy 690TT in primary water10.1016/j.corsci.2011.12.031 ↗
15. Effects of dissolved oxygen on corrosion fatigue cracking of Alloy 690 (TT) in pressurized water reactor environments10.1016/j.ijfatigue.2014.12.007 ↗
16. Corrosion fatigue results for Alloy 690 tubing in a PWR secondary environment
17. Corrosion fatigue initiation and short crack growth behaviour of austenitic stainless steels under light water reactor conditions10.1016/j.corsci.2012.02.008 ↗
18. Morra · 2015
19. Morra · 2015
20. Morra · 2011
21. Effects of alloy chemistry, cold work, and water chemistry on corrosion fatigue and stress corrosion cracking of nickel alloys and welds, U.S. Nuclear Regulatory Commission
22. Modelling and life prediction of stress corrosion cracking in sensitised stainless steel in high temperature water
23. Critical processes to model in predicting stress corrosion response in hot water
24. Investigation of the corrosion behavior of 304L and 316L stainless steels at high-temperature borated and lithiated water10.1080/00223131.2015.1125311 ↗
25. Data quality, issues, and guidelines for electrochemical corrosion potential measurement in high-temperature water10.5006/1.3277589 ↗
26. Electrochemical potential measurements under simulated BWR water chemistry conditions10.5006/1.3315913 ↗
27. A brief history of environmental cracking in hot water
28. SCC of unirradiated stainless steels and nickel alloys in hot water
29. IGSCC of non-sensitized stainless steels in high temperature water10.1016/j.jnucmat.2008.08.005 ↗
30. The effect of applied potential on the stress corrosion cracking of sensitized type 316 stainless steel in high temperature water10.1016/0010-938X(94)00142-S ↗
31. The stress corrosion cracking of type 316 stainless steel in oxygenated and chlorinated high temperature water10.1016/0010-938X(85)90010-1 ↗
32. Cyclic and SCC behavior of alloy 52m/182 weld overlay in a PWR environment
33. Environmentally assisted cracking of forged 316LN stainless steel and its weld in high temperature water10.1016/j.corsci.2018.10.032 ↗
34. dK/da effects on the SCC growth rates of nickel base alloys in high-temperature water10.1016/j.jnucmat.2018.02.032 ↗
35. Characterization of microstructure, local deformation and microchemistry in Alloy 600 heat-affected zone and stress corrosion cracking in high temperature water10.1016/j.corsci.2012.01.029 ↗
36. Plastic deformation and creep damage evaluations of type 316 austenitic stainless steels by EBSD10.1016/j.matchar.2010.05.006 ↗
37. Evaluation of residual plastic strain distribution in dissimilar metal weld by hardness mapping10.1179/1362171813Y.0000000144 ↗
38. Critical processes to model in predicting stress corrosion response in hot water
39. Marcus · 1994
40. Quantitative prediction of environmentally assisted cracking10.5006/1.3292125 ↗