Diffusional Interaction between U-10 wt.% Zr and Fe at 903K, 923K and 953K (630°C, 650°C, and 680°C)

Journal Article · Tue Apr 15 00:00:00 EDT 2014 · Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science

DOI:https://doi.org/10.1007/s11661-014-2277-2· OSTI ID:1177615

Park, K Y. ^[1]; Huang, K. ^[1]; Paz y Puente, A. ^[2]; Lee, H. S. ^[3]; Sencer, B. H. ^[4]; Kennedy, J. R. ^[4]

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1. Univ. of Central Florida, Orlando, FL (United States). Advanced Materials Processing and Analysis Ctr.
2. Northwestern Univ., Evanston, IL (United States)
3. Kyungpook National Univl, Daegu (Korea, Republic of)
4. Idaho National Laboratory (INL), Idaho Falls, ID (United States)

U-Zr metallic fuels cladded in Fe-alloys are being considered for application in an advanced Sodium-Cooled Fast Reactor (SFR) that can recycle the U-Zr fuels and minimize the long-lived actinide waste. To understand the complex fuel-cladding chemical interaction between the U-Zr metallic fuel with Fe-alloys, a systematic multicomponent diffusion study was carried out using solid-to-solid diffusion couples. The U-10 wt.% Zr vs. pure Fe diffusion couples were assembled and annealed at temperatures, 903, 923 and 953K for 96 hours. Development of microstructure, phase constituents, and compositions developed during the thermal anneals were examined by scanning electron microscopy, transmission electron microscopy and X-ray energy dispersive spectroscopy. Complex microstructure consisting of several layers that include phases such as U₆Fe, UFe₂, ZrFe₂, α-U, β-U, Zr-precipitates, Χ, ε and λ were observed. Multi-phase layers were grouped based on phase constituents and microstructure, and the layer thicknesses were measured to calculate the growth constant and activation energy. The local average compositions through the interaction layer were systematically determined, and employed to construct semi-quantitative diffusion paths on isothermal U-Zr-Fe ternary phase diagrams at respective temperatures. The diffusion paths were examined to qualitatively estimate the diffusional behavior of individual components and their interactions. Furthermore, selected area diffraction analyses were carried out to determine, for the first time, the exact crystal structure and composition of Χ, ε and λ-phases. The Χ, ε and λ-phases were identified as Pnma(62) Fe(Zr,U), I4/mcm(140) Fe(Zr,U)₂, and I4/mcm(140) U₃(Zr,Fe), respectively.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: DE-AC07-05ID14517
• OSTI ID: 1177615
• Report Number(s): INL/JOU-13-29741; TRN: US1500052
• Journal Information: Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science, Vol. 46, Issue 1; ISSN 1073-5623
• Publisher: ASM International
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
TETRAGONAL LATTICES
ORTHORHOMBIC LATTICES
DIFFUSION
FUEL-CLADDING INTERACTIONS
Ternary Alloy Systems
Temperature Range 0400-1000 K
SCANNING ELECTRON MICROSCOPY
Fast Reactors
SODIUM COOLED REACTORS
Reprocessing
Radioactive Waste Management
Minimization
Chemical Composition
Crystal Structure
Space Groups
TRANSMISSION ELECTRON MICROSCOPY
ALLOY NUCLEAR FUELS
PHASE DIAGRAMS
X RADIATION
CLADDING
ELECTRON DIFFRACTION
MICROSTRUCTURE
ACTIVATION ENERGY
IRON ALLOYS
ANNEALING
LAYERS
PRECIPITATION
SOLIDS
THICKNESS
X-RAY SPECTROSCOPY
Experimental Data
Fuel-Cladding Chemical Interactions
Interdiffusion
Transmission Electron Microscopy