Post-irradiation microstructural examination of EUROFER-ODS steel irradiated at 300°C and 400°C

Klimenkov, M.; Jäntsch, U.; Rieth, M.; Dürrschnabel, Michael; Möslang, A.; Schneider, Holger

doi:10.1016/j.jnucmat.2021.153259

Cited by 8 publications

(7 citation statements)

References 38 publications

(92 reference statements)

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“…Combining equations ( 9), ( 10), (21) with the above expression (33), we can express the non-vanishing components of the elastic stress tensor as…”

Section: Elastic Stress In An Ion-irradiated Thin Filmmentioning

confidence: 99%

“…It is either the bodycentred cubic structure characterising iron-chromium alloys, ferritic steels and tungsten, or the face-centred cubic structure of copper, copper alloys and austenitic steels [2,[14][15][16][17]. Exposure of these materials to irradiation gives rise to swelling or, in other words, to the predominantly isotropic volume expansion resulting from the accumulation of defects in the material [18][19][20][21]. In the absence of applied load or other constraints, no significant anisotropic dimensional changes are expected to occur in the crystallographically isotropic materials selected for the structural components of a fusion power plant.…”

Section: Introductionmentioning

confidence: 99%

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Macroscopic elastic stress and strain produced by irradiation

et al. 2021

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Using the notion of eigenstrain produced by the defects formed in a material exposed to high energy neutron irradiation, we develop a method for computing macroscopic elastic stress and strain arising in components of a fusion power plant during operation. In a microstructurally isotropic material, the primary cause of macroscopic elastic stress and strain fields is the spatial variation of neutron exposure. We show that under traction-free boundary conditions, the volume-average elastic stress always vanishes, signifying the formation of a spatially heterogeneous stress state, combining compressive and tensile elastic deformations at different locations in the same component, and resulting solely from the spatial variation of radiation exposure. Several case studies pertinent to the design of a fusion power plant are analysed analytically and numerically, showing that a spatially varying distribution of defects produces significant elastic stresses in ion-irradiated thin films, pressurised cylindrical tubes and breeding blanket modules.

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“…Combining equations ( 9), ( 10), (21) with the above expression (33), we can express the non-vanishing components of the elastic stress tensor as…”

Section: Elastic Stress In An Ion-irradiated Thin Filmmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Macroscopic elastic stress and strain produced by irradiation

et al. 2021

View full text Add to dashboard Cite

show abstract

“…Combining equations ( 9), ( 10), (21) with the above expression (33), we can express the non-vanishing compo-nents of the elastic stress tensor as…”

Section: Elastic Stress In An Ion-irradiated Thin Filmmentioning

confidence: 99%

“…It is either the body-centred cubic (bcc) structure characterising iron-chromium alloys, ferritic steels and tungsten, or the face-centred cubic (fcc) structure of copper, copper alloys and austenitic steels [2,[14][15][16][17]. Exposure of these materials to irradiation gives rise to swelling or, in other words, to the predominantly isotropic volume expansion resulting from the accumulation of defects in the material [18][19][20][21]. In the absence of applied load or other constraints, no significant anisotropic dimensional changes are expected to occur in the crystallographically isotropic materials selected for the structural components of a fusion power plant.…”

Section: Introductionmentioning

confidence: 99%

Macroscopic elastic stress and strain produced by irradiation

Reali,

Boleininger,

Gilbert

et al. 2021

Preprint

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“…Considering one of the significant goals for the advanced reactors is to produce economically clean energy with no long-lived high-radioactivity waste [ 10 , 11 , 12 ], the low-activation criteria should be included in the structural materials’ design of advanced reactors. Certain achievements have been made in the research of qualified low-activation materials, including oxide dispersion strengthened (ODS) steels [ 13 , 14 ], V-based alloys [ 15 , 16 ], reduced activation ferritic/martensitic (RAFM) steels [ 17 , 18 ], and China low activation martensitic (CLAM) steels [ 19 , 20 ].…”

Section: Introductionmentioning

confidence: 99%

He-ion Irradiation Effects on the Microstructures and Mechanical Properties of the Ti-Zr-Hf-V-Ta Low-Activation High-Entropy Alloys

Zhang

Wang

et al. 2023

Materials

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High-entropy alloys (HEAs) have shown promising potential applications in advanced reactors due to the outstanding mechanical properties and irradiation tolerance at elevated temperatures. In this work, the novel low-activation Ti2ZrHfxV0.5Ta0.2 HEAs were designed and prepared to explore high-performance HEAs under irradiation. The microstructures and mechanical properties of the Ti2ZrHfxV0.5Ta0.2 HEAs before and after irradiation were investigated. The results showed that the unirradiated Ti2ZrHfxV0.5Ta0.2 HEAs displayed a single-phase BCC structure. The yield strength of the Ti2ZrHfxV0.5Ta0.2 HEAs increased gradually with the increase of Hf content without decreasing the plasticity at room and elevated temperatures. After irradiation, no obvious radiation-induced segregations or precipitations were found in the transmission electron microscope results of the representative Ti2ZrHfV0.5Ta0.2 HEA. The size and number density of the He bubbles in the Ti2ZrHfV0.5Ta0.2 HEA increased with the improvement of fluence at 1023 K. At the fluences of 1 × 1016 and 3 × 1016 ions/cm2, the irradiation hardening fractions of the Ti2ZrHfV0.5Ta0.2 HEA were 17.7% and 34.1%, respectively, which were lower than those of most reported conventional low-activation materials at similar He ion irradiation fluences. The Ti2ZrHfV0.5Ta0.2 HEA showed good comprehensive mechanical properties, structural stability, and irradiation hardening resistance at elevated temperatures, making it a promising structural material candidate for advanced nuclear energy systems.

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Post-irradiation microstructural examination of EUROFER-ODS steel irradiated at 300°C and 400°C

Cited by 8 publications

References 38 publications

Macroscopic elastic stress and strain produced by irradiation

Macroscopic elastic stress and strain produced by irradiation

Macroscopic elastic stress and strain produced by irradiation

He-ion Irradiation Effects on the Microstructures and Mechanical Properties of the Ti-Zr-Hf-V-Ta Low-Activation High-Entropy Alloys

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