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  1. 1
    Tritium thermal desorption testing of nuclear graphites irradiated at fluoride-salt-cooled high-temperature reactor conditions

    Tritium thermal desorption testing of nuclear graphites irradiated at fluoride-salt-cooled high-temperature reactor conditions by Dolan, Kieran Patrick.

    Published 2019
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    Thesis
  2. 2
    Tritium retention in nuclear graphite, system-level transport, and management strategies for the fluoride-salt-cooled high-temperature reactor

    Tritium retention in nuclear graphite, system-level transport, and management strategies for the fluoride-salt-cooled high-temperature reactor by Dolan, Kieran Patrick.

    Published 2021
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    Thesis

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