Effect of implantation defects on the corrosion of 316L stainless steels in primary medium of pressurized water reactors
Source abstract
Abstract
316L samples were implanted with xenon ions in order to generate defects (characterised as cavities) in the alloy subsurface region. Their oxidation kinetics in pressurized water reactor primary water at 325 °C were determined using ion beam analyses. After a 24 h exposure, the internal oxide layer reaches a thickness equivalent to the implanted affected depth (90 nm) which does not change much for longer exposure duration. Two-stages corrosion experiments followed by secondary ion mass spectrometry analyses have revealed two oxygen diffusion regimes in the internal oxide layer, which seems to be linked with the distribution of implanted defects.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Nuclear Materials and Properties · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (29)
Show source-provided references
1. Composition, structure and properties of the oxide films fromed on the stainless steel 316L in primary type PWR environment10.1016/S0010-938X(97)00158-3 ↗
2. The mechanism and kinetics of corrosion product release from stainless steel in lithiated high-temperature water10.1016/0010-938X(87)90068-0 ↗
3. The mechanism of oxide Film formation on austenitic stainless steels in high temperature water10.1016/S0010-938X(97)00140-6 ↗
4. The composition and morphology of oxide-films formed on type-304 stainless-steel in lithiated high-temperature water10.1016/0010-938X(86)90024-7 ↗
5. 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 ↗
6. Corrosion behavior of stainless steels in simulated PWR primary water-effect of chromium content in alloys and dissolved hydrogen10.1080/18811248.2008.9711883 ↗
7. Effect of surface preparation on the corrosion of austenitic stainless steel 304L in high temperature steam and simulated PWR primary water10.1016/j.corsci.2011.12.007 ↗
8. Nanoscale characterisation of grain boundary oxidation in cold-worked stainless steels10.1016/j.corsci.2012.06.030 ↗
9. Hydrogen absorption associated with the corrosion mechanism of 316L stainless steels in primary medium of pressurized water reactor (PWR)10.1016/j.corsci.2014.04.025 ↗
10. Evolution of fine-scale defects in stainless steels neutron-irradiated at 275°C10.1016/S0022-3115(03)00002-3 ↗
11. Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS10.1016/S0022-3115(03)00003-5 ↗
12. Tomographic atom probe characterization of the microstructure of a cold worked 316 austenitic stainless steel after neutron irradiation10.1016/j.jnucmat.2008.09.015 ↗
13. Evolution of microstructure and microchemistry in cold-worked 316 stainless steels under PWR irradiation10.1080/18811248.2006.9711078 ↗
14. Microchemical and microstructural changes of austenitic steels caused by proton irradiation following helium implantation10.1016/S0022-3115(98)00338-9 ↗
15. Microstructure evolution in austenitic Fe-Cr-Ni alloys irradiated with protons: comparison with neutron-irradiated microstructures10.1016/S0022-3115(01)00615-8 ↗
16. Deformation microstructure of proton-irradiated stainless steels10.1016/j.jnucmat.2006.12.012 ↗
17. Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part I: Evolution of the microstructure10.1016/j.jnucmat.2003.11.007 ↗
18. Emulation of neutron irradiation effects with protons: validation of principle10.1016/S0022-3115(01)00751-6 ↗
19. Influence of irradiation on the oxide film formed on 316L stainless steel in PWR primary water10.1007/s11085-013-9401-3 ↗
20. The stopping and range of ions in matter
21. A detailed TEM and SEM study of Ni-base alloys oxide scales formed in primary conditions of pressurized water reactor10.1016/j.jnucmat.2010.05.010 ↗
22. Modeling of O-18 tracer distribution during double oxidation experiments for inward growing scales10.1063/1.360718 ↗
23. Role of copper and aluminum on the corrosion behavior of austenitic Fe-Mn-C TWIP steels in aqueous solutions and the related hydrogen absorption10.1016/j.corsci.2014.02.018 ↗
24. Ditribution and mobility of tritium in type 316 stainless steel10.13182/FST57-3-185 ↗
25. Edington · 1976
26. Atom-probe tomography charaterization of the oxidation of stainless steel10.1016/j.scriptamat.2010.02.021 ↗
27. Multi-scale characterization os stress corrosion cracking of cold-worked stainless steels and the inlufenc of Cr content10.1016/j.actamat.2009.07.040 ↗
28. R. Soulas, Effet de la cristallographie sur les premiers stades de l’oxydation des aciers austénitiques 316L, Thesis, Grenoble (France), 2012.
29. Electrochemical behaviour of 316L stainless steel exposed to representative chemistry in pressurised water reactors under proton radiation10.1016/j.jelechem.2014.10.015 ↗