Preliminary Design of Critical Experiments Involving Commercially Available B4C Neutron Absorber Plates with Low-Enriched UO2 Fuel

Mathieu N. Dupont, William J. Marshall, Justin B. Clarity

Research output: Contribution to journalConference articlepeer-review

Original languageEnglish
Pages (from-to)473-476
Number of pages4
JournalTransactions of the American Nuclear Society
Volume128
DOIs
StatePublished - 2023
Event2023 Transactions of the American Nuclear Society Annual Meeting and Technology Expo, ANS 2023 - Indianapolis, United States
Duration: Jun 11 2023Jun 14 2023

Funding

This work has been supported by the Nuclear Criticality Safety Program, funded and managed by the National Nuclear Security Administration for the Department of Energy.

FundersFunder number
U.S. Department of Energy
National Nuclear Security Administration

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