Interdiffusion between U-Pu-Zr fuel and HT9 cladding [electronic resource]
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Online Access: |
Online Access (via OSTI) |
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Corporate Author: | |
Format: | Government Document Electronic eBook |
Language: | English |
Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Department of Energy. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
1994.
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Subjects: |
Abstract: | As part of systematic interdiffusion studies of fuel-cladding compatibility in the integral Fast Reactor, a solid-solid diffusion couple was assembled with U-22Pu-23¹ Zr fuel and HT9² cladding and annealed at 650°C for 100 hours. The couple was examined for diffusion structure development using a scanning electron microscope equipped with an energy dispersive x-ray analyzer (SEM-EDX). Point-by-point and linescan analysis was used to generate composition profiles and diffusion paths. From the composition profiles, average effective interdiffusion coefficients were calculated for individual components on both sides of the Matano plane. Results from this investigation indicate that the same types of phases as would be expected from binary U-Fe, Pu-Fe, and Zr-Fe phase diagrams develop in this couple; and U and Pu are the fastest diffusing fuel components and Fe is the fastest diffusing cladding component. Compared with diffusion couples with binary (U-Zr) fuel, the addition of Pu greatly enhanced the extent of diffusion and affected the types of phases observed. |
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Item Description: | Published through SciTech Connect. 06/01/1994. "anl/fe/cp--82405" " conf-940631--1" "DE94012453" 34. annual conference of the Canadian Nuclear Association,Montreal (Canada),5-8 Jun 1994. Keiser, D.D. Jr. [Argonne National Lab., Idaho Falls, ID (United States)]; Petri, M.C. [Argonne National Lab., IL (United States)] |
Physical Description: | 12 p. : digital, PDF file. |