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:
-
- 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:https://doi.org/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:https://doi.org/10.1080/00295450.2019.1623617. https://www.osti.gov/servlets/purl/1578274.
@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}
}
Works referenced in this record:
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Fuels for sodium-cooled fast reactors: US perspective
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Metallic fuels for advanced reactors
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Plutonium and plutonium alloys as nuclear fuel materials
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Thermal conductivity of U–20 wt.%Pu–2 wt.%Am–10 wt.%Zr alloy
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The Thermodynamic Properties of the f-Elements and Their Compounds. I. The Lanthanide and Actinide Metals
journal, December 2010
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Migration of minor actinides and lanthanides in fast reactor metallic fuel
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The lattice stability and structure of delta -UZr 2 at elevated temperatures
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Structure of β-uranium
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- Acta Crystallographica Section B Structural Science, Vol. 44, Issue 2
Thermal expansion of rolled and extruded uranium
journal, April 1983
- Logan, R. W.; Wood, D. H.
- Journal of the Less Common Metals, Vol. 90, Issue 2
Mass spectrometric studies on U-Pu-Zr alloy
journal, August 2018
- Manikandan, P.; Trinadh, V. V.; Bera, Suranjan
- Journal of Nuclear Materials, Vol. 507
Thermodynamic activity measurements of U-Zr alloys by knudsen effusion mass spectrometry
journal, June 1988
- Kanno, Masayoshi; Yamawaki, Michio; Koyama, Tadafumi
- Journal of Nuclear Materials, Vol. 154, Issue 1
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
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
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
- Kim, Yeon Soo; Cho, Tae Won; Sohn, Dong-Seong
- Journal of Nuclear Materials, Vol. 445, Issue 1-3
Works referencing / citing this record:
The heat content and specific heat of some metallic fast-reactor fuels containing plutonium
journal, March 1968
- Savage, H.
- Journal of Nuclear Materials, Vol. 25, Issue 3
Thermodynamic activity measurements of U-Zr alloys by knudsen effusion mass spectrometry
journal, June 1988
- Kanno, Masayoshi; Yamawaki, Michio; Koyama, Tadafumi
- Journal of Nuclear Materials, Vol. 154, Issue 1
Thermal expansion of rolled and extruded uranium
journal, April 1983
- Logan, R. W.; Wood, D. H.
- Journal of the Less Common Metals, Vol. 90, Issue 2
Plutonium and plutonium alloys as nuclear fuel materials
journal, January 1971
- Kittel, J. H.; Ayer, J. E.; Beck, W. N.
- Nuclear Engineering and Design, Vol. 15
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
Mechanistic materials modeling for nuclear fuel performance
journal, July 2017
- Tonks, Michael R.; Andersson, David; Phillpot, Simon R.
- Annals of Nuclear Energy, Vol. 105
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
Metallic fuels for advanced reactors
journal, July 2009
- Carmack, W. J.; Porter, D. L.; Chang, Y. I.
- Journal of Nuclear Materials, Vol. 392, Issue 2
Migration of minor actinides and lanthanides in fast reactor metallic fuel
journal, July 2009
- Kim, Yeon Soo; Hofman, G. L.; Yacout, A. M.
- Journal of Nuclear Materials, Vol. 392, Issue 2
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
- Kim, Yeon Soo; Cho, Tae Won; Sohn, Dong-Seong
- Journal of Nuclear Materials, Vol. 445, Issue 1-3
Thermal conductivity of U–20 wt.%Pu–2 wt.%Am–10 wt.%Zr alloy
journal, September 2015
- Nishi, Tsuyoshi; Nakajima, Kunihisa; Takano, Masahide
- Journal of Nuclear Materials, Vol. 464
Mass spectrometric studies on U-Pu-Zr alloy
journal, August 2018
- Manikandan, P.; Trinadh, V. V.; Bera, Suranjan
- Journal of Nuclear Materials, Vol. 507
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
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
The lattice stability and structure of delta -UZr 2 at elevated temperatures
journal, October 1995
- Akabori, M.; Ogawa, T.; Itoh, A.
- Journal of Physics: Condensed Matter, Vol. 7, Issue 43
Structure of β-uranium
journal, April 1988
- Lawson, A. C.; Olsen, C. E.; Richardson, J. W.
- Acta Crystallographica Section B Structural Science, Vol. 44, Issue 2