U-Mo Monolithic Fuel for Nuclear Research and Test Reactors

doi:10.1007/s11837-017-2612-3

Title: U-Mo Monolithic Fuel for Nuclear Research and Test Reactors

Abstract

The metallic fuel selected to replace the current HEU fuels in the research and test reactors is the LEU-10 weight % Mo alloy in the form of a thin sheet or foil encapsulated in AA6061 aluminum alloy with a zirconium interlayer. In order to effectively lead this pursuit, new developments in processing and fabrication of the fuel elements have been initiated, along with a better understanding of material behavior before and after irradiation as a result of these new developments. This editorial note gives an introduction about research and test reactors, need for HEU to LEU conversion, fuel requirements, high uranium density monolithic fuel development and an overview of the four articles published in the December 2017 issue of JOM under a special topic titled “U-Mo Monolithic Fuel for Nuclear Research and Test Reactors”.

Authors:: Prabhakaran, Ramprashad

Publication Date:: 2017-11-02

Research Org.:: Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1415697

Report Number(s):: PNNL-SA-129341
Journal ID: ISSN 1047-4838; DN2006000

DOE Contract Number:: AC05-76RL01830

Resource Type:: Journal Article

Journal Name:: JOM. Journal of the Minerals, Metals & Materials Society

Additional Journal Information:: Journal Volume: 69; Journal Issue: 12; Journal ID: ISSN 1047-4838

Publisher:: Springer

Country of Publication:: United States

Language:: English

Subject:: U-Mo; research and test reactors; LEU fuel development

Citation Formats


                    Prabhakaran, Ramprashad. U-Mo Monolithic Fuel for Nuclear Research and Test Reactors.  United States: N. p., 2017. 
        Web.  doi:10.1007/s11837-017-2612-3.

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                    Prabhakaran, Ramprashad. U-Mo Monolithic Fuel for Nuclear Research and Test Reactors.  United States.  doi:10.1007/s11837-017-2612-3.

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                    Prabhakaran, Ramprashad. Thu .  
        "U-Mo Monolithic Fuel for Nuclear Research and Test Reactors".  United States.  doi:10.1007/s11837-017-2612-3.

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@article{osti_1415697,

  title        = {U-Mo Monolithic Fuel for Nuclear Research and Test Reactors},

  author       = {Prabhakaran, Ramprashad},

  abstractNote = {The metallic fuel selected to replace the current HEU fuels in the research and test reactors is the LEU-10 weight % Mo alloy in the form of a thin sheet or foil encapsulated in AA6061 aluminum alloy with a zirconium interlayer. In order to effectively lead this pursuit, new developments in processing and fabrication of the fuel elements have been initiated, along with a better understanding of material behavior before and after irradiation as a result of these new developments. This editorial note gives an introduction about research and test reactors, need for HEU to LEU conversion, fuel requirements, high uranium density monolithic fuel development and an overview of the four articles published in the December 2017 issue of JOM under a special topic titled “U-Mo Monolithic Fuel for Nuclear Research and Test Reactors”.},

  doi          = {10.1007/s11837-017-2612-3},

  journal      = {JOM. Journal of the Minerals, Metals & Materials Society},

  issn         = {1047-4838},

  number       = 12,

  volume       = 69,

  place        = {United States},

  year         = {2017},

  month        = {11}

}

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DOI: 10.1007/s11837-017-2612-3

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Works referenced in this record:

History of fast reactor fuel development
journal, September 1993

Kittel, J. H.; Frost, B. R. T.; Mustelier, J. P.
Journal of Nuclear Materials, Vol. 204
DOI: 10.1016/0022-3115(93)90193-3

Development of very-high-density low-enriched-uranium fuels
journal, December 1997

Snelgrove, J. L.; Hofman, G. L.; Meyer, M. K.
Nuclear Engineering and Design, Vol. 178, Issue 1
DOI: 10.1016/S0029-5493(97)00217-3

Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel
journal, August 2002

Meyer, M. K.; Hofman, G. L.; Hayes, S. L.
Journal of Nuclear Materials, Vol. 304, Issue 2-3
DOI: 10.1016/S0022-3115(02)00850-4

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Title: U-Mo Monolithic Fuel for Nuclear Research and Test Reactors

Abstract

Citation Formats

History of fast reactor fuel development journal, September 1993

Development of very-high-density low-enriched-uranium fuels journal, December 1997

Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel journal, August 2002

History of fast reactor fuel development
journal, September 1993

Development of very-high-density low-enriched-uranium fuels
journal, December 1997

Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel
journal, August 2002