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

doi:10.1080/00295450.2019.1623617

This content will become publicly available on July 2, 2020

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:

^[1];

^[1]

Idaho National Lab. (INL), Idaho Falls, ID (United States)

Publication Date:: 2019-07-02

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.

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                    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.

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                    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.

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@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}

}

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Works referenced in this record:

Mechanistic materials modeling for nuclear fuel performance
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Tonks, Michael R.; Andersson, David; Phillpot, Simon R.
Annals of Nuclear Energy, Vol. 105
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Fuels for sodium-cooled fast reactors: US perspective
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Crawford, Douglas C.; Porter, Douglas L.; Hayes, Steven L.
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Kittel, J. H.; Ayer, J. E.; Beck, W. N.
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Thermal conductivity of U–20 wt.%Pu–2 wt.%Am–10 wt.%Zr alloy
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Nishi, Tsuyoshi; Nakajima, Kunihisa; Takano, Masahide
Journal of Nuclear Materials, Vol. 464
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The Thermodynamic Properties of the f-Elements and Their Compounds. I. The Lanthanide and Actinide Metals
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Konings, Rudy J. M.; Beneš, Ondrej
Journal of Physical and Chemical Reference Data, Vol. 39, Issue 4
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Migration of minor actinides and lanthanides in fast reactor metallic fuel
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Kim, Yeon Soo; Hofman, G. L.; Yacout, A. M.
Journal of Nuclear Materials, Vol. 392, Issue 2
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The lattice stability and structure of delta -UZr ₂ at elevated temperatures
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Thermal expansion of rolled and extruded uranium
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Logan, R. W.; Wood, D. H.
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Mass spectrometric studies on U-Pu-Zr alloy
journal, August 2018

Manikandan, P.; Trinadh, V. V.; Bera, Suranjan
Journal of Nuclear Materials, Vol. 507
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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
DOI: 10.1016/0022-3115(88)90129-8

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

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

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
DOI: 10.1016/j.jnucmat.2013.11.018

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
DOI: 10.1016/0022-3115(68)90168-2

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
DOI: 10.1016/0022-3115(88)90129-8

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
DOI: 10.1016/0022-5088(83)90073-5

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
DOI: 10.1016/0029-5493(71)90076-8

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

Tonks, Michael R.; Andersson, David; Phillpot, Simon R.
Annals of Nuclear Energy, Vol. 105
DOI: 10.1016/j.anucene.2017.03.005

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

Carmack, W. J.; Porter, D. L.; Chang, Y. I.
Journal of Nuclear Materials, Vol. 392, Issue 2
DOI: 10.1016/j.jnucmat.2009.03.007

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
DOI: 10.1016/j.jnucmat.2009.03.043

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
DOI: 10.1016/j.jnucmat.2013.11.018

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
DOI: 10.1016/j.jnucmat.2015.04.043

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

Manikandan, P.; Trinadh, V. V.; Bera, Suranjan
Journal of Nuclear Materials, Vol. 507
DOI: 10.1016/j.jnucmat.2018.05.020

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

Akabori, M.; Ogawa, T.; Itoh, A.
Journal of Physics: Condensed Matter, Vol. 7, Issue 43
DOI: 10.1088/0953-8984/7/43/005

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This content will become publicly available on July 2, 2020

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

Abstract

Citation Formats

Mechanistic materials modeling for nuclear fuel performance journal, July 2017

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

Metallic fuels for advanced reactors journal, July 2009

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

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

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

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

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

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

Structure of β-uranium journal, April 1988

Thermal expansion of rolled and extruded uranium journal, April 1983

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

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

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

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

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

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

Mechanistic materials modeling for nuclear fuel performance journal, July 2017

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

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

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

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

Mechanistic materials modeling for nuclear fuel performance
journal, July 2017

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

Metallic fuels for advanced reactors
journal, July 2009

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

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

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

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

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

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

Structure of β-uranium
journal, April 1988

Thermal expansion of rolled and extruded uranium
journal, April 1983

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

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

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

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

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

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

Mechanistic materials modeling for nuclear fuel performance
journal, July 2017

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

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

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

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