Validation of OpenMC for Gen IV Graphite-Moderated Reactors: Insights from Benchmarking the UFTR

4 Nov 2025, 13:50
15m
60/Ground-103 - Lecture Hall (Administration Building)

60/Ground-103 - Lecture Hall

Administration Building

80
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Extended Abstract Reactor Physics

Description

This two-page abstract presents a benchmarking study of the OpenMC Monte Carlo code using the University of Florida Training Reactor (UFTR) as a graphite-moderated test case. It outlines the development of a high-fidelity OpenMC model, the simulation setup, and comparison with experimental reactivity data. The abstract demonstrates OpenMC’s accuracy in modeling graphite-moderated systems and discusses its potential for Generation IV reactor analysis.

Technical Track Reactor Physics

Primary authors

Mr Abdullah Alharbi (Department of Materials Science & Engineering, Nuclear Engineering Program, Herbert Wertheim College of Engineering, University of Florida) Dr Justin Watson (Department of Materials Science & Engineering, Nuclear Engineering Program, Herbert Wertheim College of Engineering, University of Florida)

Presentation materials