Hardening of SS316 Stainless Steel Caused by the Irradiation with Argon Ions

Karpov, S.A.; Tolstolutskaya, G.D.; Sungurov, B. S.; Rostova, A. Yu.; Tolmacheva, G. N.; Kopanets, I.E.

doi:10.1007/s11003-016-9967-4

Cited by 11 publications

(12 citation statements)

References 14 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Generally, irradiation assisted hardening in fcc metals is associated with the formation of Frank loops which, being sessile in nature, strongly impede the movement of dislocations [3,[18][19][20]. However, in the present study the main radiation-induced hardening effect is attributed to cavities formation.…”

Section: Eejp 2 (2021)contrasting

confidence: 49%

Microstructure and Hardening Behavior of Argon-Ion Irradiated Steels 18Cr10NiTi and 18Cr10NiTi-ODS

2021

EEJP

View full text Add to dashboard Cite

Microstructure and nanohardness evolution in 18Cr10NiTi and 18Cr10NiTi-ODS steels after exposure to argon ion irradiation has been studied by combination of nanoindentation tests, XRD analysis, TEM and SEM observation. ODS-modified alloy was produced on the basis of conventional 18Cr10NiTi austenitic steel by mechanical alloying of steel powder with Y(Zr)-nanooxides followed by mechanical-thermal treatment. XRD analysis has showed no significant changes in the structure of 18Cr10NiTi steel after irradiation at room and elevated temperatures (873 K) and in ODS-steel after irradiation at 873 K, whereas the evidences of domains refinement and microstrain appearance were revealed after irradiation of 18Cr10NiTi-ODS steel at room temperature (RT). Layer-by-layer TEM analysis was performed to investigate the microstructure of alloys along the damage profile. The higher displacement per atom (dpa) and Ar concentration clearly lead to increased cavities size and their number density in both steels. The swelling was estimated to be almost half for 18Cr10NiT-ODS (4.8%) compared to 18Cr10NiTi (9.4%) indicating improved swelling resistance of ODS-steel. The role of oxide/matrix interface as a sink for radiation-induced point defects and inert gas atoms is discussed. The fine dispersed oxide particles are considered as effective factor in suppressing of cavity coarsening and limiting defect clusters to small size. The hardness behavior was investigated in both non-irradiated and irradiated specimens and compared to those at RT and elevated temperature of irradiation. The hardness increase of unirradiated ODS-steel is associated mainly with grain refinement and yttrium oxides particles addition. The hardening of 18Cr10NiTi-ODS after Ar ion irradiation at RT was found to be much lower than 18Cr10NiTi. Black dots and dislocation loops are observed for both steels in the near-surface area; however, the main hardening effect is caused by the cavities. Oxide dispersion strengthened steel was found to be less susceptible to radiation hardening/embrittlement compared with a conventional austenitic steel.

show abstract

Section: Eejp 2 (2021)contrasting

confidence: 49%

Microstructure and Hardening Behavior of Argon-Ion Irradiated Steels 18Cr10NiTi and 18Cr10NiTi-ODS

2021

EEJP

View full text Add to dashboard Cite

show abstract

“…These values are comparable with those found in the literature. 3,4,34 For instance, Yabuuchi et al measured the hardness of unirradiated 316L stainless steel to be 1.5 GPa, with the hardness increasing to 5.3 GPa after irradiation with protons to 8 dpa. 34 Nanoindentation results in this study additionally suggest that the magnitude of irradiation hardening with damage level reached a plateau, an observation that has also been made in literature.…”

Section: Resultsmentioning

confidence: 99%

“…34 Nanoindentation results in this study additionally suggest that the magnitude of irradiation hardening with damage level reached a plateau, an observation that has also been made in literature. 3,4 The evolution of the plastic zone area during the fatigue tests is shown in Figure 4. No clear differences between irradiated and unirradiated specimens could be observed.…”

Section: Resultsmentioning

confidence: 99%

“…In austenitic steels, increases in hardness of up to 92% have been reported from heavy ion irradiation at room temperature. 3,4 In this study, a hardness increase of 63% was measured as a result of 30 MeV Ni ion irradiation at room temperature. Irradiation hardening is attributed to the increased number of dislocations, such as Frank loops, and black dots.…”

Section: Discussionmentioning

confidence: 99%

“…1 In austenitic steels, increases in hardness of up to 92% have been reported from heavy ion irradiation at room temperature. 3,4 In stainless steels, below temperatures of 300 C, black dot damage outweighs Frank dislocation loops. 5 While at greater temperatures, much larger Frank dislocation loops are observed.…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Effects of Ion Irradiation on Stage II Fatigue Crack Growth and Plasticity

Weihrauch,

Patel,

Patterson

2024

Fatigue Fract Eng Mat Struct

View full text Add to dashboard Cite

Fatigue crack growth characteristics of ion irradiated compact tension (CT) specimens were evaluated in the Paris law region. Fatigue crack growth was monitored under tension‐tension loading and the thermoelastic response was measured. Two stages of crack propagation were identified. In the first 300,000 cycles, crack growth rates of irradiated and unirradiated specimens were comparable and plastic zone area was found to be independent of crack length. Beyond 300,000 cycles, irradiated specimens showed a greater crack growth rate; additionally, the plastic zone area increased with crack length. The increase in crack growth rate was attributed to irradiation hardening. The plastic zone area was found to be dependent on the crack path, especially in the initial stages of crack propagation. Local peaks in the value of the area of the plastic zone were found to be associated with greater crack tortuosity and secondary cracks. As a result, decreases in plastic zone area were associated with greater crack growth rates.

show abstract

Oblique cross-section nanoindentation for determining the hardness change in ion-irradiated steel

Saleh

Hurt

et al. 2019

International Journal of Plasticity

View full text Add to dashboard Cite

Hardening of SS316 Stainless Steel Caused by the Irradiation with Argon Ions

Cited by 11 publications

References 14 publications

Microstructure and Hardening Behavior of Argon-Ion Irradiated Steels 18Cr10NiTi and 18Cr10NiTi-ODS

Microstructure and Hardening Behavior of Argon-Ion Irradiated Steels 18Cr10NiTi and 18Cr10NiTi-ODS

Effects of Ion Irradiation on Stage II Fatigue Crack Growth and Plasticity

Oblique cross-section nanoindentation for determining the hardness change in ion-irradiated steel

Contact Info

Product

Resources

About