Study and simulations of quick diffusion in Zr-based alloys

JOURNAL OF NUCLEAR MATERIALS

卷:466

Article

Corvalan, C.^1,2,4  Lucia, A.^1,3  Iribarren, M.^2,3  Servant, C.⁵  Costa e Silva, A.⁶ 

[1] UNTREF Univ Nacl Tres de Febrero, Gen Enrique Mosconi 2736, Buenos Aires, DF, Argentina

[2] Comis Energia Atom, CAC, Gerencia Mat, Buenos Aires, DF, Argentina

[3] Univ Nacl San Martin, Comis Nacl Energia Atom, Inst Sabato, Buenos Aires, DF, Argentina

[4] Consejo Nacl Invest Cient & Tecn, Buenos Aires, DF, Argentina

[5] Univ Paris 11, ICMMO, UMR 8182, Lab Physicochim Etat Solide, F-91405 Orsay, France

[6] Univ Fed Fluminense, Volta Redonda, RJ, Brazil

关键词: Diffusion;    Nuclear materials;    Zirconium;    DICTRA;   

DOI  :  10.1016/j.jnucmat.2015.07.024

来源: Elsevier

【 摘 要 】

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 (similar to 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 alpha-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 alpha-Zr for Cr and Co are presented in the temperature range of 380-460 K. (C) 2015 Elsevier B.V. All rights reserved.

【 授权许可】

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