Mechanical properties and microstructure of neutron irradiated cold worked Al-6063 alloy

Munitz, A.; Shtechman, A.; Cotler, C.; Talianker, M.; Dahan, Serge

doi:10.1016/s0022-3115(97)00293-6

Cited by 18 publications

(5 citation statements)

References 10 publications

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“…According to Kapusta et al [19], this loss of ductility is quantified by a reduction in total elongation; this reduction is related to the content of silicon generated under neutron flux, while strength is little affected by the high amount of silicon production. Farrell and King also found a transition from a transgranular to an intergranular ductile fracture mechanism, which is confirmed by Munitz et al [20] who found that radiation hardening of 6063 aluminium alloy is accompanied by a transition from transgranular shear fracture to intergranular fracture.…”

Section: Mechanical Properties After Irradiationsupporting

confidence: 56%

Effects of neutron irradiation and post-irradiation annealing on pop-in crack propagation instabilities in 6061 aluminium alloy

Petit

Ritter²,

Besson³

et al. 2022

Journal of Nuclear Materials

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Section: Mechanical Properties After Irradiationsupporting

confidence: 56%

Effects of neutron irradiation and post-irradiation annealing on pop-in crack propagation instabilities in 6061 aluminium alloy

Petit

Ritter²,

Besson³

et al. 2022

Journal of Nuclear Materials

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“…A substantial amount of literature is published on the irradiation behavior of Al alloys [2][3][4][5][6][7][8][9][10][11]. The available dataset on 6xxx series alloys is considerably larger due to their widespread use in several research reactors and cold-neutron sources [2,[4][5][6][7][8][9][10]. On the other hand, only limited data were found on 5xxx series alloys [3,9,11,12].…”

Section: Literature On Irradiation Effects In Al Alloysmentioning

confidence: 99%

Neutron Irradiation Effects in 5xxx and 6xxx Series Aluminum Alloys: A Literature Review

Kolluri¹

2016

Radiation Effects in Materials

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A literature review on highly irradiated 5xxx and 6xxx series Al alloys is conducted to understand the expected changes in mechanical properties of high flux reactor (HFR) vessel material in relation with microstructural aspects beyond the current surveillance data to support the HFR Surveillance Program (SURP). It was found that the irradiation swelling in 5xxx series alloys is not a crucial degradation mechanism. Dislocation damage is expected to reach a saturation limit in both 5xxx and 6xxx series alloys at relatively low fast-fluence values (<2 × 10 26 n/m 2). The damage caused by precipitation of transmutation Si is found to be the dominant mechanism affecting the fracture toughness properties of irradiated 5xxx and 6xxx series Al alloys at high thermal fluence values. Tensile and fracture toughness data collected from the literature up to very high thermal fluences are analyzed in comparison with the available HFR surveillance data to predict the behavior of the HFR vessel material beyond current surveillance data. The observed changes in mechanical properties are classified into four different regimes. The contribution of various irradiation damage mechanisms, namely the displacement damage and transmutation damage, to the evolution of microstructure and mechanical properties is discussed in all four regimes for 5xxx and 6xxx series alloys.

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“…Aluminum is widely used in structural components of research reactors, including the High Flux Isotope Reactor (HFIR), the Savannah River Laboratory (SRL), and the Oak Ridge Research Reactor (ORRR) [ 4 , 5 , 6 , 7 ]. Munitz et al [ 8 ] studied the effects of neutron irradiation on the mechanical properties and fracture morphology of Al-6063 using scanning electron microscopy (SEM), transmission electron microscopy (TEM), and the tensile tests method. Their results show that with the increase in neutron fluence, the uniform elongation and ultimate tensile strength increase, the intergranular fracture area increases, in addition to the fracture mechanism changes from ductile transgranular shear fracture to the combination of transgranular shear and intergranular dimple fracture.…”

Section: Introductionmentioning

confidence: 99%

Tensile Property of Irradiated LT21 Aluminum Alloy Sampled from Decommissioned Irradiation Channel of Heavy Water Research Reactor

et al. 2023

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LT21 a type of aluminum alloy used for the irradiation channel of the first heavy water research reactor (HWRR) in China. Studying the mechanical property of irradiated LT21 aluminum under actual service conditions is essential for evaluating its application property. In this paper, tensile specimens of irradiated LT21 were manufactured from the decommissioned irradiation channel of an HWRR; then, tensile tests were carried out, and then the fracture surfaces were observed. The effect of neutron irradiation on tensile behavior and the failure mechanism was analyzed by comparing the result of irradiated and unirradiated LT21 specimens. The results show that, with the thermal neutron flux increasing to 2.38 × 1022 n/cm2, the YS gradually increased from the initial 158 MPa to 251 MPa, the UTS increased from 262 MPa to 321 MPa, and the elongation decreased from 28.8% to about 14.3%; the brittle fracture of the LT21 specimen appeared after irradiation, and the proportion of brittle fracture increased as the neutron fluence increased; the nanophase structures, with a size of less than 50 nm, were precipitated in the LT21 aluminum alloy after neutron irradiation. Transmutation Si is presumed to be the main cause of the radiation effect mechanism of LT21.

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Mechanical properties and microstructure of neutron irradiated cold worked Al-6063 alloy

Cited by 18 publications

References 10 publications

Effects of neutron irradiation and post-irradiation annealing on pop-in crack propagation instabilities in 6061 aluminium alloy

Effects of neutron irradiation and post-irradiation annealing on pop-in crack propagation instabilities in 6061 aluminium alloy

Neutron Irradiation Effects in 5xxx and 6xxx Series Aluminum Alloys: A Literature Review

Tensile Property of Irradiated LT21 Aluminum Alloy Sampled from Decommissioned Irradiation Channel of Heavy Water Research Reactor

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