Phase Instability and Void Formation in Neutron-Irradiated Fe&amp;ndash;Cr&amp;ndash;Mn&amp;ndash;Ni Alloys

Ohnuki, Somei; Garner, F.А.; Takahashi, Hiroki

doi:10.2320/matertrans1989.34.1031

Cited by 4 publications

(4 citation statements)

References 15 publications

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“…In general, prior experimental measurements and model predictions for conventional Fe-Cr-Ni alloys suggest that significant RIS is observable at doses of ~0.1 to 1 dpa, and a tendency toward saturation occurs at higher doses (i.e., relatively small additional RIS occurs at higher doses) [79]. Overall, the grain boundary segregation trends observed in the examined HEA samples are qualitatively similar but less pronounced in magnitude compared to the behavior seen in austenitic stainless steels, where Ni enrichment and Cr and Mn depletion at grain boundaries have been reported following irradiation at intermediate temperatures in numerous prior studies [22,62,68,80]. Figure 8 (e, f) shows the experimentally observed radiation induced segregation profiles at high angle grain boundaries in the Fe-Ni-Mn-Cr HEA samples that were ion irradiated to a dose of 10 dpa at 400 and 600°C.…”

Section: Radiation Induced Segregation (Ris)mentioning

confidence: 61%

“…Voids are commonly formed in irradiated single phase materials for doses above ∼1 dpa at temperatures where vacancies are mobile, due to accumulation of radiation-induced vacancies into stable cavities [61]. Void swelling in Fe-Cr-Ni alloys at elevated temperatures (>400°C) has a significant deleterious impact on allowable lifetime and reactor operations [17,[62][63][64][65][66][67][68]. Earlier studies have shown that overall swelling of Fe-Cr-Ni alloys can be modified by varying the Ni and Cr concentration [63,68], but in general void formation is expected in conventional Fe-Cr-Ni alloys for ion irradiation doses above 1-10 dpa at 450-650°C [45,46,57,69].…”

Section: Voidsmentioning

confidence: 99%

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Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation

et al. 2016

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In recent years, high entropy alloys (HEAs) have attracted significant attention due to their excellent mechanical properties and good corrosion resistance, making them potential candidates for high temperature fission and fusion structural applications. However there is very little known about their radiation resistance, particularly at elevated temperatures relevant for energy applications. In the present study, a single phase (face centered cubic) concentrated solid solution alloy of composition 27%Fe-28%Ni-27%Mn-18%Cr was irradiated with 3 or 5.8 MeV Ni ions at temperatures ranging from room temperature to 700°C and midrange doses from 0.03 to 10 displacements per atom (dpa). Transmission electron microscopy (TEM), scanning transmission electron microscopy with energy dispersive x-ray spectrometry (STEM/EDS) and X-ray diffraction (XRD) were used to characterize the radiation defects and microstructural changes. Irradiation at higher temperatures showed evidence of relatively sluggish solute diffusion with limited solute depletion or enrichment at grain boundaries. The main microstructural feature at all temperatures was high-density small dislocation loops. Voids were not observed at any irradiation condition. Nano-indentation tests on specimens irradiated at room temperature showed a rapid increase in hardness ~35% and ~80% higher than the unirradiated value at 0.03 and 0.3 dpa midrange doses, respectively. The irradiation-induced hardening was less pronounced for 500°C irradiations (<20% increase after 3 dpa). Overall, the examined HEA material exhibits superior radiation resistance compared to conventional single phase Fe-Cr-Ni austenitic alloys such as stainless steels. The present study provides insight on the fundamental irradiation behavior of a single phase HEA material over a broad range of irradiation temperatures.

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Section: Radiation Induced Segregation (Ris)mentioning

confidence: 61%

Section: Voidsmentioning

confidence: 99%

Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation

et al. 2016

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“…Compositions based on Fe-12Cr-(20-25)Mn-0.25C [7][8][9][10], with minor alloying additions of V, W, Ti, B, P, as well as various variants of steels with similar compositions [6,[11][12][13][14], were developed. However, the austenite stability of these steels, determined by the nickel equivalent, is (17)(18)(19)(20), which is lower than that of the latest generation of chromium-nickel steels (19)(20)(21)(22)(23)(24)(25)(26). The formation of chromium-manganese steels with an addition of Ni and N for austenite stabilization, and with Mn and C, was also reported [15][16][17][18].…”

Section: Introductionmentioning

confidence: 99%

“…The presence of a significant amount of different phases in any austenitic steel is highly undesirable, as it has a negative effect on its mechanical properties. For example, a significant amount of σ-phase can cause material embrittlement [22][23][24].…”

Section: Introductionmentioning

confidence: 99%

Microstructure Features and Mechanical Properties of Modified Low-Activation Austenitic Steel in the Temperature Range of 20 to 750 °C

Litovchenko,

Akkuzin,

Polekhina

et al. 2023

Metals

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A new low-activation austenitic steel with a modified composition and high austenite stability is proposed. The features of its microstructure after solution treatment (ST) and cold rolling (CR) are studied. The mechanical properties and features of the fracture behavior of this steel under tensile tests in the temperature range of 20–750 °C are discussed. After ST, an austenitic structure with stacking faults and dispersed carbide particles of the MC and M23C6 types is observed in the steel. After CR, the grains are refined, and the average grain size decreases from 41.4 µm (after ST) to 33.9 µm. High-density microtwin packets form in the material, and the dislocation density increases relative to that after ST. As the test temperature increases from 20 to 750 °C, the yield strength of the steel decreases by approximately two times, from ≈300 to 150 MPa (for ST) and from ≈700 to 370 MPa (for CR). In the studied temperature range, the steel demonstrates up to 2.6 times higher values of elongation to failure, ≈40–80% (for ST) and ≈13–27% (for CR), compared to steels of similar compositions and lower manganese content. Mechanical twinning contributes to the high steel ductility up to 300 °C. Signs of discontinuous flow in the tensile curves after ST in the temperature range of 500–600 °C and a decrease in the elongation to failure in the close temperature range indicate dynamic strain aging (DSA). Steel fracture after tension at all test temperatures mainly occurs via a ductile dimple transcrystalline mechanism with elements of ductile intercrystalline fracture. It is shown that cracks nucleate on clusters of dispersed second-phase particles. The mechanisms of plastic deformation, fracture, and strengthening of the proposed modified low-activation austenitic steel are discussed.

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In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation

et al. 2020

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Phase Instability and Void Formation in Neutron-Irradiated Fe–Cr–Mn–Ni Alloys

Cited by 4 publications

References 15 publications

Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation

Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation

Microstructure Features and Mechanical Properties of Modified Low-Activation Austenitic Steel in the Temperature Range of 20 to 750 °C

In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation

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