Artículo
Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation
Fecha de publicación:
11/2021
Editorial:
Tech Reviews Ltd.
Revista:
Journal of Materials and Applications
e-ISSN:
2051-7750
Idioma:
Inglés
Tipo de recurso:
Artículo publicado
Clasificación temática:
Resumen
Due to low neutron absorption cross section, high mechanical strength, high thermal conductivity and good corrosion resistance in water and steam, Zirconium alloys are widely used as fuel cladding material in nuclear reactors. During life-time of a reactor the microstructure of this alloy is affected due to, among other factors, radiation damage and hydrogen damage. In this work mechanical properties changes on neutron irradiated Zr-1wt.% Nb at low temperatures (< 100 °C) and low dose (3.5 ´ 1023 n m-2 (E > 1 MeV)) were correlated with hydrides and crystal defects evolution during irradiation. To achieve this propose, tensile tests of: 1) Non-hydrided and non-irradiated material, 2) Hydrided and non-irradiated material and 3) Hydrided and irradiated material were performed at 25 ºC and 300 ºC. Different phases, hydrides and second phase precipitates were characterized by transmission electron microscopy (TEM) techniques. For the hydrided and irradiated material, the ductility decreased sharply with respect to the hydrided and non-irradiated material, among other factors, due to the change in the microstructure produced mainly by neutron irradiation. Even if the presence of the hydride ζ (zeta) was observed, both in the irradiated and non-irradiated material, tensile tests showed that ζ-hydrides did not affect ductility, since hydrided samples are more ductile than non-hydrided samples.
Palabras clave:
Zirconium alloys
,
Radiation damage
,
Hydrogen
,
Electron microscopy
,
Tensile tests
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Identificadores
Colecciones
Articulos(CCT - PATAGONIA NORTE)
Articulos de CTRO.CIENTIFICO TECNOL.CONICET - PATAGONIA NORTE
Articulos de CTRO.CIENTIFICO TECNOL.CONICET - PATAGONIA NORTE
Citación
Vazquez, Carolina; Zelaya, Maria Eugenia; Fortis, Ana Maria; Bozzano, Patricia Beatriz; Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation; Tech Reviews Ltd.; Journal of Materials and Applications; 10; 2; 11-2021; 63-72
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