Mechanical Properties of Zircaloy-2 Neutron Irradiated to High Fluence

Cogez, Lucile; Li, Wenjing; Woo, O.T.

doi:10.12943/cnr.2017.00011

Cited by 3 publications

(3 citation statements)

References 15 publications

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“…These two variants of material exhibit different slip intensities, with the higher-strength precipitate-containing material subject to slip intensities that are a factor of >2 higher than for the solid solution–strengthened version. Another striking example in the literature is slip in neutron irradiated and nonirradiated zirconium alloys ( 24 ), where an increase of yield strength by a factor of 2 due to neutron irradiation results in a substantial increase in slip intensity ( 25 ).…”

Section: Relationship Between Fatigue Strength and Slip Localizationmentioning

confidence: 99%

On the origins of fatigue strength in crystalline metallic materials

Stinville

Charpagne

Cervellon

et al. 2022

Science

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Metallic materials experience irreversible deformation with increasing applied stress, manifested in localized slip events that result in fatigue failure upon repeated cycling. We discerned the physical origins of fatigue strength in a large set of face-centered cubic, hexagonal close-packed, and body-centered cubic metallic materials by considering cyclic deformation processes at nanometer resolution over large volumes of individual materials at the earliest stages of cycling. We identified quantitative relations between the yield strength and the ultimate tensile strength, fatigue strength, and physical characteristics of early slip localization events. The fatigue strength of metallic alloys that deform by slip could be predicted by the amplitude of slip localization during the first cycle of loading. Our observations provide a physical basis for well-known empirical fatigue laws and enable a rapid method of predicting fatigue strength as reflected by measurement of slip localization amplitude.

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Section: Relationship Between Fatigue Strength and Slip Localizationmentioning

confidence: 99%

On the origins of fatigue strength in crystalline metallic materials

Stinville

Charpagne

Cervellon

et al. 2022

Science

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“…At the point where this stress locus (black dashed line) intersects the yield surface for the isotropic case (blue curve), the strain rate vector (normal to the surface) is vertical and there is no axial strain. For calandria tubes with a high radial basal texture, the uniaxial yield stress in the longitudinal and transverse directions is approximately the same [15]. For pressure tubes, the transverse yield stress is about 1.4 times larger than for the longitudinal direction, and this is because of the strong basal texture in the transverse direction [17]; see Supplementary Materials Figure S4.…”

Section: Texture-induced Flow Localisation-calandria Tube Failurementioning

confidence: 93%

“…A cut through the theoretical yield surface in the plane of the tube for an irradiated calandria tube is illustrated in Figure 4. The uniaxial yield stress in the longitudinal or transverse direction outside of the weld is approximately 700 MPa [15]. The main body of a calandria tube has a strong basal pole texture in the radial direction (indicated by the Kearns texture parameter, f d [16], where d is the component direction).…”

Section: Texture-induced Flow Localisation-calandria Tube Failurementioning

confidence: 99%

Strain Localisation and Fracture of Nuclear Reactor Core Materials

Griffiths

2023

JNE

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The production of prismatic dislocation loops in nuclear reactor core materials results in hardening because the loops impede dislocation motion. Yielding often occurs by a localised clearing of the loops through interactions with gliding dislocations called channeling. The cleared channels represent a softer material within which most of the subsequent deformation is localized. Channeling is often associated with hypothetical dislocation pileup and intergranular cracking in reactor components although the channels themselves do not amplify stress as one would expect from a pileup. The channels are often similar in appearance to twins leading to the possibility that twins are sometimes mistakenly identified as channels. Neither twins nor dislocation channels, which are bulk shears, produce the same stress conditions as a pileup on a single plane. At high doses, when cavities are produced (either He-stabilised bubbles at low temperatures or voids at high temperatures), there can be reduced ductility because the material is already in an equivalent advanced stage of microscopic necking. He-stabilised cavities form preferentially on grain boundaries and at precipitate or incoherent twin/ε-martensite interfaces. The higher planar density of the cavities, coupled with the incompatibility at the interface, results in a preferential failure known as He embrittlement. Strain localisation and inter- or intragranular failure are dependent on many factors that are ultimately microstructural in nature. The mechanisms are described and discussed in relation to reactor core materials.

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