Artículo
Study and simulations of quick diffusion in Zr-based alloys
Corvalán Moya, Carolina del Huerto
; Lucía, A.; Iribarren, Manuel José; Servant, Colette; Costa E Silva, A.
Fecha de publicación:
08/2015
Editorial:
Elsevier Science
Revista:
Journal of Nuclear Materials
ISSN:
0022-3115
Idioma:
Inglés
Tipo de recurso:
Artículo publicado
Clasificación temática:
Resumen
Zirconium and its alloys are widely used in the nuclear industry. Under normal conditions, Zr-alloys are polycrystalline and contain a high density of grain and interphase boundaries. These boundaries function as paths for accelerated matter movement. The movement of fast diffusing elements (Co, Fe, Cr, Ni) in Zr alloys along boundaries produces technologically important changes in the materials in nuclear reactors at normal temperatures (∼550 K) e.g.: segregation, phase precipitation, hydrogen absorption, etc. In this work, diffusion parameters for fast diffusion in Zr at low temperature were assessed for Co and Cr. An improved database for DICTRA (DIffusion-Controlled-TRAnsformation) software for fast diffusion was obtained. The diffusion parameters in grain boundaries of α-Zr for Cr and Co were used from a particular kinetic diffusion model [1]. Simulated profiles were compared with previous experimental work [2]. The results of the comparison and the adequacy of the improved database are discussed. Diffusion profiles on grain boundaries in α-Zr for Cr and Co are presented in the temperature range of 380-460 K.
Palabras clave:
DICTRA
,
DIFFUSION
,
NUCLEAR MATERIALS
,
ZIRCONIUM
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Articulos(SEDE CENTRAL)
Articulos de SEDE CENTRAL
Articulos de SEDE CENTRAL
Citación
Corvalán Moya, Carolina del Huerto; Lucía, A.; Iribarren, Manuel José; Servant, Colette; Costa E Silva, A.; Study and simulations of quick diffusion in Zr-based alloys; Elsevier Science; Journal of Nuclear Materials; 466; 8-2015; 80-84
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