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Title: Mechanical properties examined by nanoindentation for selected phases relevant to the development of monolithic uranium-molybdenum metallic fuels

Nanomechanical properties, specifically the reduced modulus and hardness of several intermetallic and solid solution phases are reported here to assist the development of the U-10 wt% Mo (U-10Mo) monolithic fuel system for research and test reactors. Findings from this study and reported values of mechanical properties provide data critical for understanding and predicting the structural behavior of the fuel system during fabrication and irradiation. The phases examined are products of interdiffusion and reaction between (1) the AA6061 cladding and the Zr diffusion barrier, namely (Al,Si) 3Zr and Al 3Zr, (2) the U-10Mo fuel and the Zr diffusion barrier, namely UZr 2, Mo 2Zr, and a-U, and (3) the U (or U-10Mo) and Mo, namely a mixture gradient of α- and γ-phases. The UC inclusions observed within the fuel alloy were also examined. Only phases present in thick or continuous microstructure on cross-sectioned fuel plates and diffusion couples were investigated for reduced modulus and hardness. Concentration-dependence of room-temperature reduced modulus in U solid solution with 0–10 wt% Mo was semi-quantitatively modeled based on mixture of α- and γ-phases and solid solutioning within the γ-phase.
Authors:
ORCiD logo [1] ;  [1] ;  [1] ;  [2] ;  [1]
  1. Univ. of Central Florida, Orlando, FL (United States). Dept. of Materials Science and Engineering
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States). Nuclear Fuels and Materials Division
Publication Date:
Report Number(s):
INL/JOU-17-41448
Journal ID: ISSN 0022-3115; PII: S0022311516306092
Grant/Contract Number:
AC07-05ID14517
Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 487; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Research Org:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation (NA-20)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 77 NANOSCIENCE AND NANOTECHNOLOGY; monolithic uranium-molybdenum metallic fuels; nanoindentation
OSTI Identifier:
1405302
Alternate Identifier(s):
OSTI ID: 1396890

Newell, Ryan, Park, Youngjoo, Mehta, Abhishek, Keiser, Dennis, and Sohn, Yongho. Mechanical properties examined by nanoindentation for selected phases relevant to the development of monolithic uranium-molybdenum metallic fuels. United States: N. p., Web. doi:10.1016/j.jnucmat.2017.02.018.
Newell, Ryan, Park, Youngjoo, Mehta, Abhishek, Keiser, Dennis, & Sohn, Yongho. Mechanical properties examined by nanoindentation for selected phases relevant to the development of monolithic uranium-molybdenum metallic fuels. United States. doi:10.1016/j.jnucmat.2017.02.018.
Newell, Ryan, Park, Youngjoo, Mehta, Abhishek, Keiser, Dennis, and Sohn, Yongho. 2017. "Mechanical properties examined by nanoindentation for selected phases relevant to the development of monolithic uranium-molybdenum metallic fuels". United States. doi:10.1016/j.jnucmat.2017.02.018. https://www.osti.gov/servlets/purl/1405302.
@article{osti_1405302,
title = {Mechanical properties examined by nanoindentation for selected phases relevant to the development of monolithic uranium-molybdenum metallic fuels},
author = {Newell, Ryan and Park, Youngjoo and Mehta, Abhishek and Keiser, Dennis and Sohn, Yongho},
abstractNote = {Nanomechanical properties, specifically the reduced modulus and hardness of several intermetallic and solid solution phases are reported here to assist the development of the U-10 wt% Mo (U-10Mo) monolithic fuel system for research and test reactors. Findings from this study and reported values of mechanical properties provide data critical for understanding and predicting the structural behavior of the fuel system during fabrication and irradiation. The phases examined are products of interdiffusion and reaction between (1) the AA6061 cladding and the Zr diffusion barrier, namely (Al,Si)3Zr and Al3Zr, (2) the U-10Mo fuel and the Zr diffusion barrier, namely UZr2, Mo2Zr, and a-U, and (3) the U (or U-10Mo) and Mo, namely a mixture gradient of α- and γ-phases. The UC inclusions observed within the fuel alloy were also examined. Only phases present in thick or continuous microstructure on cross-sectioned fuel plates and diffusion couples were investigated for reduced modulus and hardness. Concentration-dependence of room-temperature reduced modulus in U solid solution with 0–10 wt% Mo was semi-quantitatively modeled based on mixture of α- and γ-phases and solid solutioning within the γ-phase.},
doi = {10.1016/j.jnucmat.2017.02.018},
journal = {Journal of Nuclear Materials},
number = C,
volume = 487,
place = {United States},
year = {2017},
month = {2}
}