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Title: Experimentally Known Properties of U-10Zr Alloys: A Critical Review

More than 14000 U-10Zr fuel rods (alloys of U with 10 wt% Zr) Zr were been irradiated in the Experimental Breeder Reactor II and Fast Flux Test Facility, with some irradiated to burnups of almost 20 at%. However, very little information about properties of un-irradiated U-10Zr alloys is available. This data is needed to help with interpretation of data from irradiated materials, develop and validate phase diagrams and models of U-Zr and more complex systems, develop and validate fuel-performance codes, design fuels for future fast reactors, and design future experimental investigations to fill in crucial gaps in knowledge. This paper provides a summary and critical review of the available experimental data on phases and phase diagrams, electrical properties, thermal expansion, thermal conductivity, heat capacity, mechanical properties, vapor pressures, and thermodynamic properties of un-irradiated U-10Zr alloys. As a result, much of this data was published before ~1970 and is available only in obscure reports.
Authors:
ORCiD logo [1] ; ORCiD logo [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Report Number(s):
INL/JOU-17-44020-Rev000
Journal ID: ISSN 0029-5450
Grant/Contract Number:
AC07-05ID14517
Type:
Accepted Manuscript
Journal Name:
Nuclear Technology
Additional Journal Information:
Journal Volume: 203; Journal Issue: 2; Journal ID: ISSN 0029-5450
Publisher:
Taylor & Francis - formerly American Nuclear Society (ANS)
Research Org:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; metallic nuclear fuel; uranium-zirconium alloys; thermophysical properties; phase diagrams
OSTI Identifier:
1478233

Janney, Dawn E., and Hayes, Steven L.. Experimentally Known Properties of U-10Zr Alloys: A Critical Review. United States: N. p., Web. doi:10.1080/00295450.2018.1435137.
Janney, Dawn E., & Hayes, Steven L.. Experimentally Known Properties of U-10Zr Alloys: A Critical Review. United States. doi:10.1080/00295450.2018.1435137.
Janney, Dawn E., and Hayes, Steven L.. 2018. "Experimentally Known Properties of U-10Zr Alloys: A Critical Review". United States. doi:10.1080/00295450.2018.1435137. https://www.osti.gov/servlets/purl/1478233.
@article{osti_1478233,
title = {Experimentally Known Properties of U-10Zr Alloys: A Critical Review},
author = {Janney, Dawn E. and Hayes, Steven L.},
abstractNote = {More than 14000 U-10Zr fuel rods (alloys of U with 10 wt% Zr) Zr were been irradiated in the Experimental Breeder Reactor II and Fast Flux Test Facility, with some irradiated to burnups of almost 20 at%. However, very little information about properties of un-irradiated U-10Zr alloys is available. This data is needed to help with interpretation of data from irradiated materials, develop and validate phase diagrams and models of U-Zr and more complex systems, develop and validate fuel-performance codes, design fuels for future fast reactors, and design future experimental investigations to fill in crucial gaps in knowledge. This paper provides a summary and critical review of the available experimental data on phases and phase diagrams, electrical properties, thermal expansion, thermal conductivity, heat capacity, mechanical properties, vapor pressures, and thermodynamic properties of un-irradiated U-10Zr alloys. As a result, much of this data was published before ~1970 and is available only in obscure reports.},
doi = {10.1080/00295450.2018.1435137},
journal = {Nuclear Technology},
number = 2,
volume = 203,
place = {United States},
year = {2018},
month = {4}
}