Low-temperature thermally-activated deformation and irradiation softening in neutron-irradiated molybdenum

Li, Meimei; Byun, Thak Sang; Snead, Lance Lewis; Zinkle, S.J.

doi:10.1016/j.jnucmat.2008.03.017

Cited by 10 publications

(4 citation statements)

References 31 publications

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“…5 shows the estimated yield stress as a function of the elastic strain rate for diameters ranging from 370 nm to 3 m. The elastic strain rate sensitivity, reflected by the slope of the fit lines, varied between 0.07 and 0.1 for all diameters and loading rates tested. This is in close agreement with published data on the strain rate dependence of the yield stress for bulk bcc Mo, which shows a strain rate sensitivity slope of 0.085 [34].…”

Section: Figssupporting

confidence: 92%

“…where v is activation volume for a thermally activated process, m is a constant taken to be the Taylor factor [34,47], k is Boltzmann's constant, T is temperature,ε is strain rate, and is stress, the activation volume for each orientation was calculated. For all pillars tested, the activation volumes were found to be in the range of 1.3b 3 to 5.3b 3 , where b is the Burgers vector for Mo (2.73 Å).…”

Section: Discussionmentioning

confidence: 99%

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Effect of orientation and loading rate on compression behavior of small-scale Mo pillars

Schneider

Clark

Frick

et al. 2009

Materials Science and Engineering: A

131

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Section: Figssupporting

confidence: 92%

Section: Discussionmentioning

confidence: 99%

Effect of orientation and loading rate on compression behavior of small-scale Mo pillars

Schneider

Clark

Frick

et al. 2009

Materials Science and Engineering: A

131

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“…It is, in general, essential to investigate correlations between the microstructure and properties of materials [16]. Over recent decades, irradiation hardening and embrittlement have been widely observed in nuclear structural materials with different crystalline structures [15,[17][18][19][20], e.g., facecentered cubic (FCC) [21][22][23][24], body-centered cubic (BCC) [25][26][27] and hexagonal closepacked (HCP) [28][29][30] materials [31]. Crystals present both translational and orientational properties of symmetry, which govern their physical properties [32].…”

Section: Introductionmentioning

confidence: 99%

Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels

Rodríguez-Prieto

Callejas²,

Primera

et al. 2022

Mathematics

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The aim of this work is to present a new analytical model to evaluate jointly the mechanical integrity and the fitness-for-service of nuclear reactor pressure-vessels steels. This new methodology integrates a robust and regulated irradiation embrittlement prediction model such as the ASTM E-900 with the ASME Fitness-for-Service code used widely in other demanding industries, such as oil and gas, to evaluate, among others, the risk of experiencing degradation mechanisms such as the brittle fracture (generated, in this case, due to the irradiation embrittlement). This multicriteria analytical model, which is based on a new formulation of the brittle fracture criterion, allows an adequate prediction of the irradiation effect on the fracture toughness of reactor pressure-vessel steels, letting us jointly evaluate the mechanical integrity and the fitness-for-service of the vessel by using standardized limit conditions. This allows making decisions during the design, manufacturing and in-service of reactor pressure vessels. The results obtained by the application of the methodology are coherent with several historical experimental works.

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“…Over recent decades, irradiation-hardening and embrittlement have been widely observed in nuclear structural materials with different crystalline structures [1][2][3][4], e.g., face-centered cubic (FCC) [5][6][7][8], body-centered cubic (BCC) [9][10][11] and hexagonal close-packed (HCP) [12][13][14][15] materials. Compared with their unirradiated counterparts, the yield stress or hardness of irradiated materials tends to increase with the irradiation dose (see Figure 1a,b for instance) until the density of irradiation-induced defects gets saturated.…”

Section: Introductionmentioning

confidence: 99%

Fundamental Mechanisms for Irradiation-Hardening and Embrittlement: A Review

Xiao

2019

Metals

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It has long been recognized that exposure to irradiation environments could dramatically degrade the mechanical properties of nuclear structural materials, i.e., irradiation-hardening and embrittlement. With the development of numerical simulation capability and advanced experimental equipment, the mysterious veil covering the fundamental mechanisms of irradiation-hardening and embrittlement has been gradually unveiled in recent years. This review intends to offer an overview of the fundamental mechanisms in this field at moderate irradiation conditions. After a general introduction of the phenomena of irradiation-hardening and embrittlement, the formation of irradiation-induced defects is discussed, covering the influence of both irradiation conditions and material properties. Then, the dislocation-defect interaction is addressed, which summarizes the interaction process and strength for various defect types and testing conditions. Moreover, the evolution mechanisms of defects and dislocations are focused on, involving the annihilation of irradiation defects, formation of defect-free channels, and generation of microvoids and cracks. Finally, this review closes with the current comprehension of irradiation-hardening and embrittlement, and aims to help design next-generation irradiation-resistant materials.

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Low-temperature thermally-activated deformation and irradiation softening in neutron-irradiated molybdenum

Cited by 10 publications

References 31 publications

Effect of orientation and loading rate on compression behavior of small-scale Mo pillars

Effect of orientation and loading rate on compression behavior of small-scale Mo pillars

Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels

Fundamental Mechanisms for Irradiation-Hardening and Embrittlement: A Review

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