Crack growth behavior of warm-rolled 316L austenitic stainless steel in high-temperature hydrogenated water
Source abstract
Abstract
Abstract To investigate the effects of warm rolling on the crack growth of 316L austenitic stainless steel, the crack growth rate was measured and the oxide structure was characterized in high-temperature hydrogenated water. The warm-rolled specimens showed a higher crack growth rate compared to the as-received specimens because the slip bands and dislocations produced during warm rolling served as paths for corrosion and cracking. The crack growth rate increased with the dissolved hydrogen concentration. This may be attributed to the decrease in performance and stability of the protective oxide layer formed on the surface of stainless steel in high-temperature water.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Corrosion Behavior and Inhibition · Nuclear Materials and Properties
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (40)
Show source-provided references
1. Sickafus · 2007
2. A review of irradiation assisted stress corrosion cracking10.1016/0022-3115(94)90360-3 ↗
3. Chung · 2006
4. Importance of molybdenum on irradiation-assisted stress corrosion cracking in austenitic stainless steels10.5006/1.3284828 ↗
5. Radiation-induced segregation in irradiated Type 304 stainless steels10.1016/0022-3115(92)90503-D ↗
6. Effects of neutron irradiation on corrosion and segregation behavior in austenitic stainless steels10.1016/0022-3115(91)90275-C ↗
7. Emulation of neutron irradiation effects with protons: validation of principle10.1016/S0022-3115(01)00751-6 ↗
8. The effects of intermediate temperature irradiation on the mechanical behavior of 300-series austenitic stainless steels10.1016/0022-3115(91)90152-W ↗
9. Influence of dissolved hydrogen on structure of oxide film on alloy 600 formed primary water of pressurized water reactors10.1080/18811248.2003.9715385 ↗
10. Morton · 1999
11. Morton · 2001
12. SCC initiation testing of alloy 600 in high temperature water
13. Stress corrosion cracking on irradiated 316 stainless steel10.1016/S0022-3115(00)00704-2 ↗
14. Effects of temperature, hydrogen and boric acid concentration on IGSCC susceptibility of annealed 316 stainless steel
15. Behavior of stainless steels in pressurized water reactor primary circuits10.1016/j.jnucmat.2012.03.034 ↗
16. Cold rolling effect on the microstructure and pitting resistance of the NBR ISO 5832-1 austenitic stainless steel10.1016/S1452-3981(23)13308-6 ↗
17. IGSCC crack growth in simulated BWR environment – effect of nitrogen content in non-sensitized and warm rolled austenitic stainless steel10.1016/j.corsci.2010.12.012 ↗
18. ASTM E647-12 · 2012
19. Corrosion fatigue crack growth behavior of austenitic stainless steels under light water reactor conditions10.1016/j.corsci.2011.10.005 ↗
20. J.H. Kim, R.G. Ballinger and P.W. Stahle. SCC Crack Growth in 316L Weld Metals in BWR Environments, Nace - International Corrosion Conference Series, March 16-20, 2008.10.5006/C2008-08600 ↗
21. Stress corrosion cracking crack growth behavior of Type 316L stainless steel weld metals in boiling water reactor environments10.5006/1.3279925 ↗
22. Effect of thermal aging on SCC and mechanical properties of stainless steel weld metals
23. Effects of hydrogen on stress corrosion crack growth of Ni alloys in high-temperature water10.5006/1.3278508 ↗
24. Environmentally assisted growth rate response of nonsensitized AISI 316 grade stainless steel in high temperature water10.5006/1.3583961 ↗
25. SCC of cold-worked austenitic stainless steels in PWR conditions
26. Weld decay in AISI 304 stainless steel
27. Influence of cold working on the pitting corrosion resistance of stainless steels10.1016/j.corsci.2006.08.021 ↗
28. Scanning electrochemical microscopy part 13. Evaluation of the tip shapes of nanometer size microelectrodes10.1016/0022-0728(92)80169-5 ↗
29. Corrosion fatigue behavior of cold-worked 304L stainless steel in a simulated BWR coolant environment10.2320/matertrans.MRA2008402 ↗
30. Khatak · 2002
31. Influence of carbide precipitation and rolling direction on intergranular stress corrosion cracking of austenitic stainless steels in hydrogenated high-temperature water10.5006/1.3280670 ↗
32. Magnetic force microscopy of fatigue crack tip region in a316L stainless steel10.1016/S1359-6462(02)00138-0 ↗
33. Corrosion B behavior of stainless steels in simulated PWR primary water—effect of chromium content in alloys and dissolved hydrogen10.1080/18811248.2008.9711883 ↗
34. Effects of dissolved hydrogen content in PWR primary water on PWSCC initiation property
35. Morton · 2012
36. SCC growth behaviors of austenitic stainless steels in simulated PWR primary water10.1016/j.jnucmat.2012.03.013 ↗
37. Hydride formation and decomposition in electrolytically charged metastable austenitic stainless steels10.1007/BF02647744 ↗
38. Photoelectrochemical study of hydrogen-loaded passive film10.1149/1.1591759 ↗
39. Microstructural characterization of SCC crack tip and oxide film for SUS 316 stainless steel in simulated PWR primary water at 320°C10.1080/18811248.2005.9726383 ↗
40. The point defect model for the passive state10.1149/1.2069096 ↗