Burnup and spatially dependent uranium isotopic calculations for the high flux isotope reactor

David Chandler, R. T. Primm, G. Ivan Maldonado

Research output: Contribution to journalConference articlepeer-review

1 Scopus citations

Abstract

A uranium/molybdenum fuel is under development for the purpose of converting U.S. research reactors to low enriched fuel. Nuclear fuel depletion tools and methodologies have been utilized and benchmarked in order to support the conversion of the High Flux Isotope Reactor from high enriched uranium to low enriched uranium. Post-irradiation uranium isotopic atomic densities within the core of HFIR were calculated and compared to uranium mass spectrographic data measured in the late 1960s and early 70s. The ALEPH and VESTA Monte Carlo based depletion tools were employed for time- and spatially-dependent nuclide inventory calculations.

Original languageEnglish
Pages (from-to)768-769
Number of pages2
JournalTransactions of the American Nuclear Society
Volume103
StatePublished - 2010
Externally publishedYes
Event2010 ANS Annual Meeting and Embedded Topical Meeting: Isotopes for Medicine and Industry - Las Vegas, NV, United States
Duration: Nov 7 2010Nov 11 2010

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