Neutronics feasibility study for conversion of the high flux isotope reactor with LEU U-7Mo dispersion fuel

    Research output: Contribution to journalConference articlepeer-review

    1 Scopus citations
    Original languageEnglish
    Pages (from-to)620-622
    Number of pages3
    JournalTransactions of the American Nuclear Society
    Volume96
    StatePublished - 2007
    Event2007 Annual Meeting on American Nuclear Society - Boston, MA, United States
    Duration: Jun 24 2007Jun 28 2007

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