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  1. 1
    Centrifugal pumps for sodium cooled reactors /

    Centrifugal pumps for sodium cooled reactors / by Kale, R. D., Sreedhar, B. K.

    Published 2024
    Full Text (via Taylor & Francis)
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  2. 2
    Sodium fast reactors with closed fuel cycle /

    Sodium fast reactors with closed fuel cycle / by Raj, Baldev, 1947-2018, Chellapandi, P., Vasudeva Rao, P. R.

    Published 2015
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  3. 3
    Status of fast reactor research and technology development.

    Status of fast reactor research and technology development.

    Published 2012
    Full Text (via Knovel)
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  4. 4
    Centrifugal pumps for sodium cooled reactors /

    Centrifugal pumps for sodium cooled reactors / by Kale, R. D., Sreedhar, B. K.

    Published 2024
    Full Text (via Taylor & Francis)
    Electronic eBook
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  5. 5
    Molten salt vs. liquid sodium receiver selection using the analytic hierarchy process /

    Molten salt vs. liquid sodium receiver selection using the analytic hierarchy process / by Turchi, Craig S. (Craig Steven)

    Published 2021
    Online Access
    Government Document eBook
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  6. 6
    Status and trends of nuclear fuels technology for sodium cooled fast reactors.

    Status and trends of nuclear fuels technology for sodium cooled fast reactors.

    Published 2011
    Book
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  7. 7
    Status and trends of nuclear fuels technology for sodium cooled fast reactors

    Status and trends of nuclear fuels technology for sodium cooled fast reactors

    Published 2011
    Online Access
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  8. 8
    Benchmark analyses on the control rod withdrawal tests performed during the Phénix end-of-life experiments : report of a coordinated research project 2008-2011.

    Benchmark analyses on the control rod withdrawal tests performed during the Phénix end-of-life experiments : report of a coordinated research project 2008-2011.

    Published 2014
    Book
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  9. 9
    Benchmark analyses on the natural circulation test performed during the Phenix end-of-life experiments : final report of a coordinated research project 2008-2011.

    Benchmark analyses on the natural circulation test performed during the Phenix end-of-life experiments : final report of a coordinated research project 2008-2011.

    Published 2013
    Book
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  10. 10
    Sodium fast reactors with closed fuel cycle /

    Sodium fast reactors with closed fuel cycle / by Raj, Baldev, 1947-2018, Chellapandi, P., Vasudeva Rao, P. R.

    Published 2015
    Full Text (via ProQuest)
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  11. 11
    Benchmark analysis of EBR-II shutdown heat removal tests.

    Benchmark analysis of EBR-II shutdown heat removal tests.

    Published 2017
    Book
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  12. 12
    Comparison of containment systems for large sodium-cooled breeder reactors /

    Comparison of containment systems for large sodium-cooled breeder reactors / by Seeman, S. E.

    Published 1978
    Government Document Book
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  13. 13
    Sodium flow distribution in test fuel assembly P-23B /

    Sodium flow distribution in test fuel assembly P-23B / by Taylor, J. P. S.

    Published 1978
    Government Document Book
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  14. 14
    Benefits and challenges of small modular fast reactors : proceedings of a technical meeting.

    Benefits and challenges of small modular fast reactors : proceedings of a technical meeting.

    Published 2021
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  15. 15
    Benefits and challenges of small modular fast reactors : proceedings of a technical meeting.

    Benefits and challenges of small modular fast reactors : proceedings of a technical meeting.

    Published 2021
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  16. 16
    Status of fast reactor research and technology development.

    Status of fast reactor research and technology development.

    Published 2012
    Book
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  17. 17
    Benchmark analysis of EBR-II shutdown heat removal tests

    Benchmark analysis of EBR-II shutdown heat removal tests

    Published 2017
    Online Access
    Electronic eBook
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  18. 18
    Sodium-cooled fast reactor (SFR)

    Sodium-cooled fast reactor (SFR)

    Published 2007
    Online Access
    Online Access
    Government Document Electronic eBook
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  19. 19
    Preapplication safety evaluation report for the power reactor innovative small module (PRISM) liquid-metal reactor final report.

    Preapplication safety evaluation report for the power reactor innovative small module (PRISM) liquid-metal reactor final report.

    Published 1994
    Government Document Microfilm Book
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  20. 20
    Status of fast reactor research and technology development.

    Status of fast reactor research and technology development.

    Published 2012
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