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Evaluation of the delayed hydrogen cracking behavior and the hydrogen diffusion coefficient for different microstructures of the Zr-2.5%Nb alloy

cnea.tipodocumentoARTÍCULO CIENTÍFICO
dc.contributor.authorGomez, Adrian Guillermo
dc.contributor.authorPáez Ponce, Jose
dc.contributor.authorGrosse, M.
dc.contributor.authorSoria, Sergio Raul
dc.contributor.authorCondo, Adriana Maria
dc.contributor.authorFlores, Alejandra
dc.contributor.authorSchulz, Michael
dc.contributor.authorVizcaino, Pablo
dc.contributor.authorSantisteban, Javier Roberto
dc.date.accessioned2025-12-11T23:31:41Z
dc.date.available2025-12-11T23:31:41Z
dc.date.issued2023-12
dc.description.abstractThe susceptibility of delayed hydride cracking (DHC) in the Zr-2.5%Nb alloy was evaluated in six microstructures produced from an extruded tube of Zr-2.5%Nb, which underwent different thermomechanical treatments, divided into two separate groups: Low temperature samples (LT) were heat-treated below the monotectoid temperature in the α-Zr + β-Nb field, and included pressure tube sample of CANDU-type material obtained through two different cold deformation methods, rolling and drawing, and stress-relieved at 400 °C for 24 h, and heat-treated samples at 600 °C/4 h. High-temperature samples (HT) were heat-treated in the β-Zr field at 900 °C/3 h, and two different cooling sequences up to room temperature. The increase in the ultimate tensile strength (UTS) and hardness due to metallurgical processing in LT materials made them more susceptible to DHC, reducing the stress intensity, KIH, from 11.8 to 8.5 MPa m0.5, together with an increase in crack propagation velocity from 1.6 10−8 to 4.5 10−8 m/s. In situ hydrogen diffusion experiments were performed at ANTARES, the cold neutron imaging facility at the FRM-2 reactor, on LT materials. These experiments demonstrated that the recrystallization treatment-induced discontinuity of the β-Zr phase in the parent material has a significant impact on hydrogen diffusion. It results in a 35% reduction in the diffusion coefficient compared to the parent material and a decrease in the terminal solid solubility (TSS) was observed. This resulted in a slight increase in KIH (7%), an increase in the hydride incubation time, and a decrease of about 20% in the crack propagation velocity. Under identical testing conditions, HT specimens were not susceptible to DHC phenomenon.
dc.description.institutionalaffiliationFil: Gomez, Adrian Guillermo. Comisión Nacional de Energía Atómica. Gerencia de Área de Aplicaciones de la Tecnología Nuclear. Gerencia Ciclo del Combustible Nuclear. Laboratorio de Materia de la Fábrica de Aleaciones Especiales; Argentina
dc.description.institutionalaffiliationFil: Páez Ponce, Jose. Comisión Nacional de Energía Atómica. Gerencia de Área de Aplicaciones de la Tecnología Nuclear. Gerencia Ciclo del Combustible Nuclear. Laboratorio de Materia de la Fábrica de Aleaciones Especiales; Argentina
dc.description.institutionalaffiliationFil: Grosse, M.. Karlsruher Institut Für Technology.; Alemania
dc.description.institutionalaffiliationFil: Soria, Sergio Raul. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; Argentina
dc.description.institutionalaffiliationFil: Condo, Adriana Maria. Comisión Nacional de Energía Atómica. Centro Atómico Bariloche; Argentina. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina
dc.description.institutionalaffiliationFil: Flores, Alejandra. Comisión Nacional de Energía Atómica. Gerencia de Área de Aplicaciones de la Tecnología Nuclear. Gerencia Ciclo del Combustible Nuclear. Laboratorio de Materia de la Fábrica de Aleaciones Especiales; Argentina
dc.description.institutionalaffiliationFil: Schulz, Michael. Karlsruher Institut Für Technology.; Alemania
dc.description.institutionalaffiliationFil: Vizcaino, Pablo. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Gerencia de Área de Aplicaciones de la Tecnología Nuclear. Gerencia Ciclo del Combustible Nuclear. Laboratorio de Materia de la Fábrica de Aleaciones Especiales; Argentina
dc.description.institutionalaffiliationFil: Santisteban, Javier Roberto. Consejo Nacional de Investigaciones Científicas y Técnicas; Argentina. Comisión Nacional de Energía Atómica. Gerencia de Área de Aplicaciones de la Tecnología Nuclear. Gerencia Ciclo del Combustible Nuclear. Laboratorio de Materia de la Fábrica de Aleaciones Especiales; Argentina
dc.identifier.issn0022-3115
dc.identifier.urihttps://nuclea.cnea.gob.ar/handle/20.500.12553/8505
dc.publisherElsevier Science
dc.relationinfo:eu-repo/semantics/reference/hdl/11336/220004
dc.relationinfo:eu-repo/semantics/altIdentifier/url/https://linkinghub.elsevier.com/retrieve/pii/S0022311523004920
dc.relationinfo:eu-repo/semantics/altIdentifier/doi/http://dx.doi.org/10.1016/j.jnucmat.2023.154725
dc.rights.licenseinfo:eu-repo/semantics/restrictedAccess
dc.rights.licensehttps://creativecommons.org/licenses/by-nc-sa/2.5/ar/
dc.subjectDELAYED HYDRIDE CRACKING
dc.subjectHYDROGEN DIFFUSION
dc.subjectPRESSURE TUBES
dc.subjectZR ALLOYS
dc.subjectOtras Ingeniería de los Materiales
dc.subjectIngeniería de los Materiales
dc.subjectINGENIERÍAS Y TECNOLOGÍAS
dc.titleEvaluation of the delayed hydrogen cracking behavior and the hydrogen diffusion coefficient for different microstructures of the Zr-2.5%Nb alloy
dc.typeARTÍCULO
dc.type.versionVersión publicada

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