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

Journal Article · · Journal of Nuclear Materials
 [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
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.
Research Organization:
Idaho National Laboratory, Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation (NA-20)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1405302
Alternate ID(s):
OSTI ID: 22688982
OSTI ID: 1396890
Report Number(s):
INL/JOU--17-41448; PII: S0022311516306092
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 487; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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Cited By (1)

Mechanical Properties of U-Cu Intermetallic Compound Measured by Nanoindentation journal November 2018

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