Study on the mechanical properties evolution of A508-3 steel under proton irradiation

Jing, Lei; Ding, Hui; Shu, Guogang; Wan, Qiang-mao

doi:10.1016/j.nimb.2014.07.030

Cited by 25 publications

(5 citation statements)

References 20 publications

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“…Meanwhile, a smaller magnitude of irradiation-induced hardening was observed in the P92 steel irradiated at 400 • C. Therefore, point defects and other defect clusters should be taken into consideration to understand the magnitude of irradiation-induced hardening in P92 steel irradiated at 200 and 400 • C with the exception of dislocation loops. It was suggested that irradiation-induced defects with a small size contributing to irradiation hardening could not be observed due to the resolution limit of TEM [40]. It can be speculated that irradiation hardening in P92 steel irradiated at 200 • C is attributed to the production of both dislocation loops and other fine irradiation defects.…”

Section: Discussionmentioning

confidence: 99%

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Evaluation of Irradiation Hardening of P92 Steel under Ar Ion Irradiation

Liu

Shen

Zhu³

et al. 2018

Metals

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P92 steel was irradiated with Ar ion up to 10 dpa at 200, 400, and 700 • C. The effect of Ar ion irradiation on hardness was investigated with nanoindentation tests and microstructure analyses. It was observed that irradiation-induced hardening occurred in the steel after Ar ion irradiation at all three temperatures to 10 dpa. The steel exhibited significant hardening at 200 and 700 • C, and slight hardening at 400 • C under Ar ion irradiation. Difference in the magnitude of irradiation-induced hardening at different temperature in the steel is attributed to different changes in the microstructure of the steel that arose from the irradiation. Irradiation-induced hardening in the P92 steel irradiated at 200 • C is attributed to the occurrence of both dislocation loops and other fine irradiation defects during irradiation. Slight hardening in the steel irradiated at 400 • C mainly arises from the annihilation of defect clusters at this temperature. The occurrence of fine Ar bubbles with high number density during the Ar ion irradiation at 700 • C resulted in the significant hardening in the steel.

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Section: Discussionmentioning

confidence: 99%

“…Metals 2018, 8, x FOR PEER REVIEW 6 of 9 observed due to the resolution limit of TEM [40]. It can be speculated that irradiation hardening in P92 steel irradiated at 200 °C is attributed to the production of both dislocation loops and other fine irradiation defects.…”

Section: Discussionmentioning

confidence: 99%

Evaluation of Irradiation Hardening of P92 Steel under Ar Ion Irradiation

Liu

Shen

Zhu³

et al. 2018

Metals

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“…Figure 2 shows the depth distribution of displacement damage, which was simulated by the Stopping and Range of Ions in Matter (SRIM)-2008 software with quick mode [19]. The displacement energy of Fe atom was selected as 40 eV [20]. After Fe + implantation, total fluence of 1.4 × 10 14 Fe + /cm 2 , 3.5 × 10 14 Fe + /cm 2 and 7.0 × 10 14 Fe + /cm 2 leads to the accumulated irradiation damage of 0.2 dpa, 0.5 dpa and 1.0 dpa, respectively.…”

Section: Methodsmentioning

confidence: 99%

Ion Irradiation-Induced Microstructural Evolution of Ni–Mo–Cr Low Alloy Steels

et al. 2018

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As leading candidates of sheet steels for advanced nuclear reactors, three types of Ni–Mo–Cr high-strength low alloy (HSLA) steels named as CNST1, CNST2 and CNSS3 were irradiated by 400 keV Fe+ with peak fluence to 1.4 × 1014, 3.5 × 1014 and 7.0 × 1014 ions/cm2, respectively. The distribution and morphology of the defects induced by the sample preparation method and Fe+ irradiation dose were investigated by transmission electron microscopy (TEM) and positron-annihilation spectroscopy (PAS). TEM samples were prepared with two methods, i.e., a focused ion beam (FIB) technique and the electroplating and twin-jet electropolishing (ETE) method. Point defects and dislocation loops were observed in CNST1, CNST2 and CNSS3 samples prepared via FIB. On the other hand, samples prepared via the ETE method revealed that a smaller number of defects was observed in CNST1, CNST2 and almost no defects were observed in CNST3. It is indicated that artifact defects could be introduced by FIB preparation. The PAS S-W plots showed that the existence of two types of defects after ion implantation included small-scale defects such as vacancies, vacancy clusters, dislocation loops and large-sized defects. The S parameter of irradiated steels showed a clear saturation in PAS response with increasing Fe+ dose. At the same irradiation dose, higher values of the S-parameter were achieved in CNST1 and CNST2 samples when compared to that in CNSS3 samples. The mechanism and evolution behavior of irradiation-induced defects were analyzed and discussed.

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“…The increment of strength (∆σ y ) can be converted to the increment of hardness (∆H n ) by using the Rice equation [42] as follows:…”

Section: Aptmentioning

confidence: 99%

Effects of Fe-Ions Irradiation on the Microstructure and Mechanical Properties of FeCrAl-1.5wt.% ZrC Alloys

Wang

Zhu

et al. 2021

Nanomaterials

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Fe-13Cr-3.5Al-2.0Mo-1.5wt.% ZrC alloy was irradiated by 400 keV Fe+ at 400 °C at different doses ranging from 6.35 × 1014 to 1.27 × 1016 ions/cm2 with a corresponding damage of 1.0–20.0 dpa, respectively, to investigate the effects of different radiation doses on the hardness and microstructure of the reinforced FeCrAl alloys in detail by nanoindentation, transmission electron microscopy (TEM), and atom probe tomography (APT). The results show that the hardness at 1.0 dpa increases from 5.68 to 6.81 GPa, which is 19.9% higher than a non-irradiated specimen. With an increase in dose from 1.0 to 20.0 dpa, the hardness increases from 6.81 to 8.01 GPa, which is an increase of only 17.6%, indicating that the hardness has reached saturation. TEM and APT results show that high-density nano-precipitates and low-density dislocation loops forme in the 1.0 dpa region, compared to the non-irradiated region. Compared with 1.0 dpa region, the density and size of nano-precipitates in the 20.0 dpa region have no significant change, while the density of dislocation loops increases. Irradiation results in a decrease of molybdenum and carbon in the strengthening precipitates (Zr, Mo) (C, N), and the proportionate decrease of molybdenum and carbon is more obvious with the increase in damage.

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Study on the mechanical properties evolution of A508-3 steel under proton irradiation

Cited by 25 publications

References 20 publications

Evaluation of Irradiation Hardening of P92 Steel under Ar Ion Irradiation

Evaluation of Irradiation Hardening of P92 Steel under Ar Ion Irradiation

Ion Irradiation-Induced Microstructural Evolution of Ni–Mo–Cr Low Alloy Steels

Effects of Fe-Ions Irradiation on the Microstructure and Mechanical Properties of FeCrAl-1.5wt.% ZrC Alloys

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