Neutronic and thermal-hydraulic design studies for high flux isotope reactor conversion to low-enriched uranium high density silicide dispersion fuel

J. W. Bae, B. R. Betzler, D. Chandler, G. Has, J. L. Meszaros

Research output: Contribution to journalConference articlepeer-review

Original languageEnglish
Pages (from-to)315-318
Number of pages4
JournalTransactions of the American Nuclear Society
Volume123
Issue number1
DOIs
StatePublished - 2020
Event2020 Transactions of the American Nuclear Society Winter Meeting, ANS 2020 - Virtual, Online, United States
Duration: Nov 16 2020Nov 20 2020

Funding

'Notice: This manuscript has been authored by UT-Battelle. LLC, under contract DE-AC05-0OOR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up. irrevocable, worldwide license to publish or reproduce Ihe published form of this manuscript, or allowr others to do so. for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with thc DOE Public Access Plan (http://energy.gov/downloads/doe public access plan). This work was funded/supported by the US DOE NNSA Office of M\ The authors thank Kara Godsey and Eva Davidson for technical review of this paper.

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