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Title: Texture Evolution in U-10Mo Nuclear Fuel Foils during Plasma Spray Coating with Zr

Abstract

A uranium-molybdenum alloy clad in 6061 aluminum has the potential to lead to a wide application of low-enriched uranium fuels, replacing highly enriched uranium for research reactors. A Zr coating acts as a diffusion barrier between the fuel and the aluminum cladding. In this study, U-10Mo (mass %) was coated with Zr using a plasma spray technique recognized as a fast and economical coating method. Neutron time-of-flight diffraction was used to study the microstructure evolution by quantifying the phase fractions of involved phases as well as the texture evolution of U-10Mo and Zr during plasma spray coating with Zr. Quantitative texture analysis revealed that the texture was drastically changed for high coating temperatures, likely due to selective grain growth. Furthermore, the Zr coating showed a preferential orientation, which could be correlated with the initial texture of the uncoated U-10Mo. This could be explained by the epitaxial growth of the Zr on the U-10Mo substrate.

Authors:
 [1];  [1];  [1];  [1];  [1]; ORCiD logo [1]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1483529
Report Number(s):
LA-UR-18-23413
Journal ID: ISSN 2412-382X
Grant/Contract Number:  
AC52-06NA25396
Resource Type:
Accepted Manuscript
Journal Name:
Quantum Beam Science
Additional Journal Information:
Journal Volume: 2; Journal Issue: 2; Journal ID: ISSN 2412-382X
Publisher:
MDPI
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Neutron diffraction, U-10Mo

Citation Formats

Takajo, Shigehiro, Hollis, Kendall J., Cummins, Dustin R., Tegtmeier, Eric L., Dombrowski, David E., and Vogel, Sven C. Texture Evolution in U-10Mo Nuclear Fuel Foils during Plasma Spray Coating with Zr. United States: N. p., 2018. Web. doi:10.3390/qubs2020012.
Takajo, Shigehiro, Hollis, Kendall J., Cummins, Dustin R., Tegtmeier, Eric L., Dombrowski, David E., & Vogel, Sven C. Texture Evolution in U-10Mo Nuclear Fuel Foils during Plasma Spray Coating with Zr. United States. doi:10.3390/qubs2020012.
Takajo, Shigehiro, Hollis, Kendall J., Cummins, Dustin R., Tegtmeier, Eric L., Dombrowski, David E., and Vogel, Sven C. Wed . "Texture Evolution in U-10Mo Nuclear Fuel Foils during Plasma Spray Coating with Zr". United States. doi:10.3390/qubs2020012. https://www.osti.gov/servlets/purl/1483529.
@article{osti_1483529,
title = {Texture Evolution in U-10Mo Nuclear Fuel Foils during Plasma Spray Coating with Zr},
author = {Takajo, Shigehiro and Hollis, Kendall J. and Cummins, Dustin R. and Tegtmeier, Eric L. and Dombrowski, David E. and Vogel, Sven C.},
abstractNote = {A uranium-molybdenum alloy clad in 6061 aluminum has the potential to lead to a wide application of low-enriched uranium fuels, replacing highly enriched uranium for research reactors. A Zr coating acts as a diffusion barrier between the fuel and the aluminum cladding. In this study, U-10Mo (mass %) was coated with Zr using a plasma spray technique recognized as a fast and economical coating method. Neutron time-of-flight diffraction was used to study the microstructure evolution by quantifying the phase fractions of involved phases as well as the texture evolution of U-10Mo and Zr during plasma spray coating with Zr. Quantitative texture analysis revealed that the texture was drastically changed for high coating temperatures, likely due to selective grain growth. Furthermore, the Zr coating showed a preferential orientation, which could be correlated with the initial texture of the uncoated U-10Mo. This could be explained by the epitaxial growth of the Zr on the U-10Mo substrate.},
doi = {10.3390/qubs2020012},
journal = {Quantum Beam Science},
number = 2,
volume = 2,
place = {United States},
year = {2018},
month = {5}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record

Figures / Tables:

Figure 1 Figure 1: Infrared (IR) camera temperature data for sample 151014.

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Operational texture analysis
journal, February 1991


Dynamic study of secondary recrystallization of 3% Si-Fe by synchrotron x-radiation topography
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Effect of Initial Grain Sizes on Strain Induced Boundary Migration
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The Effect of Dislocations in Grains on Texture Formation in Strain Induced Boundary Migration
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    Works referencing / citing this record:

    Preparation and Performance Optimization of Original Aluminum Ash Coating Based on Plasma Spraying
    journal, November 2019


    Advanced Postirradiation Characterization of Nuclear Fuels Using Pulsed Neutrons
    journal, November 2019


      Figures/Tables have been extracted from DOE-funded journal article accepted manuscripts.