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Title: Effects of Cr and Ni on Interdiffusion and Reaction between U and Fe-Cr-Ni Alloys

Abstract

Metallic U-alloy fuel cladded in steel has been examined for high temperature fast reactor technology wherein the fuel cladding chemical interaction is a challenge that requires a fundamental and quantitative understanding. In order to study the fundamental diffusional interactions between U with Fe and the alloying effect of Cr and Ni, solid-to-solid diffusion couples were assembled between pure U and Fe, Fe–15 wt.%Cr or Fe–15 wt.%Cr–15 wt.%Ni alloy, and annealed at high temperature ranging from 580 to 700 °C. The microstructures and concentration profiles that developed from the diffusion anneal were examined by scanning electron microscopy, and X-ray energy dispersive spectroscopy (XEDS), respectively. Thick U6Fe and thin UFe2 phases were observed to develop with solubilities: up to 2.5 at.% Ni in U6(Fe,Ni), up to 20 at.%Cr in U(Fe, Cr)2, and up to 7 at.%Cr and 14 at.% Ni in U(Fe, Cr, Ni)2. The interdiffusion and reactions in the U vs. Fe and U vs. Fe–Cr–Ni exhibited a similar temperature dependence, while the U vs. Fe–Cr diffusion couples, without the presence of Ni, yielded greater activation energy for the growth of intermetallic phases – lower growth rate at lower temperature but higher growth rate at higher temperature.

Authors:
; ; ; ; ; ;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
1132588
Report Number(s):
INL/JOU-13-30687
Journal ID: ISSN 0022-3115
DOE Contract Number:
DE-AC07-05ID14517
Resource Type:
Journal Article
Resource Relation:
Journal Name: Journal of Nuclear Materials; Journal Volume: 451; Journal Issue: 1 - 3
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Alloying Effects; Fuel-Cladding Chemical Interactions; Interdiffusion Flux

Citation Formats

K. Huang, Y. Park, L. Zhou, K.R. Coffey, Y.H. Sohn, B.H. Sencer, and J. R. Kennedy. Effects of Cr and Ni on Interdiffusion and Reaction between U and Fe-Cr-Ni Alloys. United States: N. p., 2014. Web. doi:10.1016/j.jnucmat.2014.04.009.
K. Huang, Y. Park, L. Zhou, K.R. Coffey, Y.H. Sohn, B.H. Sencer, & J. R. Kennedy. Effects of Cr and Ni on Interdiffusion and Reaction between U and Fe-Cr-Ni Alloys. United States. doi:10.1016/j.jnucmat.2014.04.009.
K. Huang, Y. Park, L. Zhou, K.R. Coffey, Y.H. Sohn, B.H. Sencer, and J. R. Kennedy. Fri . "Effects of Cr and Ni on Interdiffusion and Reaction between U and Fe-Cr-Ni Alloys". United States. doi:10.1016/j.jnucmat.2014.04.009.
@article{osti_1132588,
title = {Effects of Cr and Ni on Interdiffusion and Reaction between U and Fe-Cr-Ni Alloys},
author = {K. Huang and Y. Park and L. Zhou and K.R. Coffey and Y.H. Sohn and B.H. Sencer and J. R. Kennedy},
abstractNote = {Metallic U-alloy fuel cladded in steel has been examined for high temperature fast reactor technology wherein the fuel cladding chemical interaction is a challenge that requires a fundamental and quantitative understanding. In order to study the fundamental diffusional interactions between U with Fe and the alloying effect of Cr and Ni, solid-to-solid diffusion couples were assembled between pure U and Fe, Fe–15 wt.%Cr or Fe–15 wt.%Cr–15 wt.%Ni alloy, and annealed at high temperature ranging from 580 to 700 °C. The microstructures and concentration profiles that developed from the diffusion anneal were examined by scanning electron microscopy, and X-ray energy dispersive spectroscopy (XEDS), respectively. Thick U6Fe and thin UFe2 phases were observed to develop with solubilities: up to 2.5 at.% Ni in U6(Fe,Ni), up to 20 at.%Cr in U(Fe, Cr)2, and up to 7 at.%Cr and 14 at.% Ni in U(Fe, Cr, Ni)2. The interdiffusion and reactions in the U vs. Fe and U vs. Fe–Cr–Ni exhibited a similar temperature dependence, while the U vs. Fe–Cr diffusion couples, without the presence of Ni, yielded greater activation energy for the growth of intermetallic phases – lower growth rate at lower temperature but higher growth rate at higher temperature.},
doi = {10.1016/j.jnucmat.2014.04.009},
journal = {Journal of Nuclear Materials},
number = 1 - 3,
volume = 451,
place = {United States},
year = {Fri Aug 01 00:00:00 EDT 2014},
month = {Fri Aug 01 00:00:00 EDT 2014}
}