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Title: A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 2: Thermal and Mechanical Properties

Abstract

Although U-Pu-Zr alloys have been investigated for more than 60 years, relatively little experimental information is available, and many of the original values are in government reports that appeared more than 40 years ago. Information about the technologically important alloy U-20Pu-10Zr (wt%) is even more limited. U-Pu-Zr alloys are difficult materials to study experimentally, and it is therefore important to understand what results have already been obtained, how reliable they are, and where they were reported. This paper provides a summary and critical assessment of the available experimental measurements of thermal and mechanical properties of U-Pu-Zr alloys. Knowledge of these properties is crucial for understanding and modeling fuel constituent redistribution, fuel swelling and creep, fission gas release under normal reactor operations, and melting or formation of liquid phases under reactor transient scenarios. This paper builds on a previous paper that assessed experimental data about phases and phase diagrams in U-Pu-Zr alloys. Both papers are intended as resources for fuel designers and modelers and as guides for prioritizing future experimental work.

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1578274
Report Number(s):
INL/JOU-18-52146-Rev002
Journal ID: ISSN 0029-5450
Grant/Contract Number:  
AC07-05ID14517
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Technology
Additional Journal Information:
Journal Volume: 206; Journal Issue: 1; Journal ID: ISSN 0029-5450
Publisher:
Taylor & Francis - formerly American Nuclear Society (ANS)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; metallic fuels; uranium-plutonium-zirconium alloys; thermal properties; mechanical properties

Citation Formats

Janney, Dawn E., Hayes, Steven L., and Adkins, Cynthia A. A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 2: Thermal and Mechanical Properties. United States: N. p., 2019. Web. doi:10.1080/00295450.2019.1623617.
Janney, Dawn E., Hayes, Steven L., & Adkins, Cynthia A. A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 2: Thermal and Mechanical Properties. United States. doi:10.1080/00295450.2019.1623617.
Janney, Dawn E., Hayes, Steven L., and Adkins, Cynthia A. Tue . "A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 2: Thermal and Mechanical Properties". United States. doi:10.1080/00295450.2019.1623617.
@article{osti_1578274,
title = {A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 2: Thermal and Mechanical Properties},
author = {Janney, Dawn E. and Hayes, Steven L. and Adkins, Cynthia A.},
abstractNote = {Although U-Pu-Zr alloys have been investigated for more than 60 years, relatively little experimental information is available, and many of the original values are in government reports that appeared more than 40 years ago. Information about the technologically important alloy U-20Pu-10Zr (wt%) is even more limited. U-Pu-Zr alloys are difficult materials to study experimentally, and it is therefore important to understand what results have already been obtained, how reliable they are, and where they were reported. This paper provides a summary and critical assessment of the available experimental measurements of thermal and mechanical properties of U-Pu-Zr alloys. Knowledge of these properties is crucial for understanding and modeling fuel constituent redistribution, fuel swelling and creep, fission gas release under normal reactor operations, and melting or formation of liquid phases under reactor transient scenarios. This paper builds on a previous paper that assessed experimental data about phases and phase diagrams in U-Pu-Zr alloys. Both papers are intended as resources for fuel designers and modelers and as guides for prioritizing future experimental work.},
doi = {10.1080/00295450.2019.1623617},
journal = {Nuclear Technology},
number = 1,
volume = 206,
place = {United States},
year = {2019},
month = {7}
}

Journal Article:
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Works referenced in this record:

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    Works referencing / citing this record:

    The heat content and specific heat of some metallic fast-reactor fuels containing plutonium
    journal, March 1968


    Thermodynamic activity measurements of U-Zr alloys by knudsen effusion mass spectrometry
    journal, June 1988


    Thermal expansion of rolled and extruded uranium
    journal, April 1983


    Plutonium and plutonium alloys as nuclear fuel materials
    journal, January 1971


    Vaporization behavior of plutonium-zirconium binary alloy
    journal, March 1994

    • Maeda, Atsushi; Suzuki, Yasufumi; Okamoto, Yoshihiro
    • Journal of Alloys and Compounds, Vol. 205, Issue 1-2
    • DOI: 10.1016/0925-8388(94)90761-7

    Mechanistic materials modeling for nuclear fuel performance
    journal, July 2017


    Fuels for sodium-cooled fast reactors: US perspective
    journal, September 2007

    • Crawford, Douglas C.; Porter, Douglas L.; Hayes, Steven L.
    • Journal of Nuclear Materials, Vol. 371, Issue 1-3
    • DOI: 10.1016/j.jnucmat.2007.05.010

    Metallic fuels for advanced reactors
    journal, July 2009


    Migration of minor actinides and lanthanides in fast reactor metallic fuel
    journal, July 2009


    Thermal conductivities of actinides (U, Pu, Np, Cm, Am) and uranium-alloys (U–Zr, U–Pu–Zr and U–Pu–TRU–Zr)
    journal, February 2014


    Thermal conductivity of U–20 wt.%Pu–2 wt.%Am–10 wt.%Zr alloy
    journal, September 2015


    Mass spectrometric studies on U-Pu-Zr alloy
    journal, August 2018


    The Thermodynamic Properties of the f-Elements and Their Compounds. I. The Lanthanide and Actinide Metals
    journal, December 2010

    • Konings, Rudy J. M.; Beneš, Ondrej
    • Journal of Physical and Chemical Reference Data, Vol. 39, Issue 4
    • DOI: 10.1063/1.3474238

    Development of Fast Reactor Metal Fuels Containing Minor Actinides
    journal, April 2011

    • Ohta, Hirokazu; Ogata, Takanari; Papaioannou, Dimitrios
    • Journal of Nuclear Science and Technology, Vol. 48, Issue 4
    • DOI: 10.1080/18811248.2011.9711746

    The lattice stability and structure of delta -UZr 2 at elevated temperatures
    journal, October 1995