Title

Characterization Of Interaction Layer In U-Mo-X (X = Nb, Zr) And U-Nb-Zr Vs. Al Diffusion Couples Annealed At 600°C For 10 Hours

Keywords

Diffusion; Fuel-cladding interaction; Metallic nuclear fuels; Uranium alloys

Abstract

U-Mo has thus far proven to be one of the most feasible metallic fuel alloys for use in research and test reactors due to its high density and stability during irradiation. However, an adverse diffusional interaction can occur between the fuel alloy and the Al based matrix. This forms an interaction layer (IL) that has undesirable thermal properties and irradiation behavior leading to accelerated swelling and reduced fuel efficiency. This study focused on the effects of ternary alloying additions on the formation of IL between U based alloys and Al. Diffusion couples of U-8Mo-3Nb, U-7Mo-6Zr, and U-10Nb-4Zr (wt.%) vs. pure Al were assembled and annealed at 600°C for 10 hours. Both thickness and phase constituent analyses were performed via electron microscopy. The major phase constituent of the IL was determined to be the UAl3 intermetallic compound. The Nb and Zr alloying additions did not reduce growth rate of IL (1.3∼1.4 μm/sec1/2) as compared to couples made between binary U-Mo and Al (0.9∼1.8 μm/sec1/2). © (2011) Trans Tech Publications.

Publication Date

1-1-2011

Publication Title

Defect and Diffusion Forum

Volume

312-315

Number of Pages

1055-1062

Document Type

Article; Proceedings Paper

Personal Identifier

scopus

DOI Link

https://doi.org/10.4028/www.scientific.net/DDF.312-315.1055

Socpus ID

79955863699 (Scopus)

Source API URL

https://api.elsevier.com/content/abstract/scopus_id/79955863699

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