IASCC of 304 SS in BWR environments: Effects of post-irradiation annealing and surface condition
Source abstract
Abstract
To investigate the impact of low-temperature post-irradiation annealing (PIA) on the stress corrosion cracking of neutron-irradiated 304 stainless steel, constant extension rate tests were conducted in simulated boiling water reactor normal water chemistry (BWR-NWC) and hydrogenated water chemistry (HWC) environments. Ten tensile samples, comprising five as-irradiated and five PIA specimens, were prepared by electropolishing the gauge section of electric discharge machined (EDM) samples. The annealing treatment reduced the yield strength from approximately 550 MPa to around 425 MPa and significantly restored the ductility and the strain hardening capability of the alloy. Consequently, the susceptibility of this material to irradiation-assisted stress corrosion cracking (IASCC) was effectively mitigated, which is more prominent in HWC, as evident from fractography, which indicated a decreased propensity for intergranular (IG) fracture. Furthermore, it was observed that the polished surface facilitated crack initiation more readily than the EDM surface, suggesting that the EDM process suppressed crack initiation to some extent.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Non-Destructive Testing Techniques
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (36)
Show source-provided references
1. Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals10.1016/S0022-3115(99)00075-6 ↗
2. Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels10.1016/S0022-3115(02)00719-5 ↗
3. How irradiation promotes intergranular stress corrosion crack initiation10.1016/j.pmatsci.2024.101255 ↗
4. Post-irradiation annealing effects on hardness and intergranular corrosion in type 304 stainless steel. Seventh international symposium on environmental degradation of materials in nuclear power systems
5. Effects of low-temperature annealing on the microstructure and grain boundary chemistry of irradiated type 304SS and correlation with IASCC
6. Microstructural changes induced by post-irradiation annealing of neutron-irradiated austenitic stainless steels10.1016/S0022-3115(00)00072-6 ↗
7. Separation of microstructural and microchemical effects in irradiation assisted stress corrosion cracking using post-irradiation annealing10.1080/18811248.2004.9726351 ↗
8. Influence of post irradiation annealing on the mechanical properties and defect structure of AISI 304 steel10.1016/j.jnucmat.2011.04.006 ↗
9. Post-irradiation annealing behavior of microstructure and hardening of a reactor pressure vessel steel studied by positron annihilation and atom probe tomography10.1016/j.jnucmat.2011.10.019 ↗
10. Evolution of the radiation-induced defect structure in 316 type stainless steel after post-irradiation annealing10.1016/j.jnucmat.2014.04.024 ↗
11. Effect of post-irradiation annealing on the irradiated microstructure of neutron-irradiated 304L stainless steel10.1016/j.jnucmat.2017.12.030 ↗
12. Low-temperature annealing: a process to mitigate irradiation-assisted stress corrosion cracking10.5006/1.3293549 ↗
13. Effects of post-irradiation annealing on the IASCC susceptibility of neutron-irradiated 304L stainless steel10.1016/j.jnucmat.2019.151755 ↗
14. Karlsen · 2014
15. Investigation of beltline welding seam of the greifswald WWER-440 Unit 1 reactor pressure vessel10.1520/JAI101925 ↗
16. On thermal annealing of irradiated PWR pressure vessels10.1016/S0308-0161(97)00078-1 ↗
17. Evaluation of the recovery annealing of the reactor pressure vessel of NPP nord (Greifswald) units 1 and 2 by means of subsize impact specimens
18. The effect of post-irradiation annealing on the stress corrosion crack growth rate of neutron-irradiated 304L stainless steel in boiling water reactor environment10.1016/j.corsci.2019.108183 ↗
19. Effects of chloride and oxygen on stress corrosion cracking of cold worked 316/316L austenitic stainless steel in high temperature water10.1016/j.corsci.2016.04.035 ↗
20. Material reliability program: development of material constitutive model for irradiated austenitic stainless steels (MRP-135-Rev. 1)
21. Irradiation-induced precipitates in a neutron irradiated 304 stainless steel studied by three-dimensional atom probe10.1016/j.jnucmat.2011.07.027 ↗
22. Microchemical and microstructural evolution of AISI 304 stainless steel irradiated in EBR-II at PWR-relevant dpa rates10.1016/j.jnucmat.2015.10.041 ↗
23. Microstructural characterization of cold-worked 316 stainless steel flux thimble tubes irradiated up to 100 dpa in a commercial pressurized water reactor10.1016/j.jnucmat.2020.152400 ↗
24. A review of irradiation effects on LWR core internal materials – IASCC susceptibility and crack growth rates of austenitic stainless steels10.1016/j.jnucmat.2010.12.001 ↗
25. Insights into the sources of irradiation hardening in a neutron irradiated 304L stainless steel following post-irradiation annealing10.1016/j.jnucmat.2019.151754 ↗
26. Crack initiation behavior of neutron irradiated model and commercial stainless steels in high temperature water10.1016/j.jnucmat.2013.10.008 ↗
27. IASCC susceptibility and slow tensile properties of highly-irradiated 316 stainless steels10.1080/18811248.2004.9715532 ↗
28. Stress corrosion cracking of irradiated stainless steels in simulated PWR primary water
29. Irradiation-assisted stress corrosion cracking10.1515/corrrev.2011.020 ↗
30. Post-irradiation annealing effects of austenitic stainless steels in IASCC
31. Effect of machining on stress corrosion crack initiation in warm-forged type 304L stainless steel in high temperature water10.1016/j.actamat.2018.11.046 ↗
32. Stress corrosion crack initiation in machined type 316L austenitic stainless steel in simulated pressurized water reactor primary water10.1016/j.corsci.2018.04.003 ↗
33. Stress corrosion crack initiation of alloy 600 in PWR primary water10.1016/j.corsci.2017.04.013 ↗
34. Effect of the surface grinding on the environmentally assisted crack initiation of 316L steel in simulated PWR water10.1115/1.4043099 ↗
35. Effect of electro discharge machining (EDM) on the AISI316L SS white layer microstructure and corrosion resistance10.1007/s00170-012-4156-6 ↗
36. Research of surface microstructure of the steel 40CrNiMo after EDM10.1088/1757-899X/754/1/012007 ↗