Benjamin R Betzler

Benjamin R Betzler

Reactor Physics Nuclear Engineer


Dr. Benjamin R. Betzler is a Research and Development staff member in the Reactor Physics group at Oak Ridge National Laboratory. His research interests include numerical methods for solving neutron transport problems (Monte Carlo transport, alpha-eigenvalue methods, methods for solving time-dependent problems, and matrix methods and applications of Markov processes) and analysis and methods development for advanced reactor designs (molten salt reactors, high-temperature gas-cooled reactors, space propulsion systems, and accelerator-driven subcritical systems). Dr. Betzler received his Ph.D in Nuclear Engineering and Radiological Sciences from the University of Michigan in 2014.


Molten Salt Reactor Modeling and Simulation
High Flux Isotope Reactor Low Enriched Uranium Conversion Project
Fuel Cycle Options Campaign
Nuclear Thermal Propulsion Modeling and Simulation
SCALE ORIGEN Reactor Libraries


Selected (see CV for full publications list):

B. R. Betzler, D. Chandler, E. E. Davidson (née Sunny), and G. Ilas, “High Fidelity Modeling and Simulation for a High Flux Isotope Reactor Low-Enriched Uranium Core Design,” Nuclear Science and Engineering, 187(1), pp. 81–99 (2017).

N. R. Brown, B. R. Betzler, J. J. Carbajo, A. J. Wysocki, M. S. Greenwood, C. A. Gentry, and A. L. Qualls, “Pre-Conceptual Design of a Fluoride High Temperature Salt-Cooled Engineering Demonstration Reactor: Core Design and Safety Analysis,” Annals of Nuclear Energy, 103, pp. 49–59 (2017).

B. R. Betzler, J. J. Powers, and A. Worrall, “Molten Salt Reactor and Fuel Cycle Modeling and Simulation with SCALE,” Annals of Nuclear Energy, 101, pp. 489–503 (2017).

B. R. Betzler and J. J. Powers, "Fully Ceramic Microencapsulated Fuels for Space Reactor Applications," Proc. PHYSOR 2016 { Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5 (2016).

B. R. Betzler, B. C. Kiedrowski, F. B. Brown, and W. R. Martin, "Calculating Infi nite-medium α-eigenvalue Spectra with Monte Carlo using a Transition Rate Matrix Method," Nucl. Eng. & Des., 295, pp. 639-644 (2015).

B. R. Betzler, B. J. Ade, D. Chandler, et al., "Optimization of Depletion Modeling and Simulation for the High Flux Isotope Reactor," Proc. ANS Mathematics & Computation Topical Mtg., Nashville, TN, USA, Apr. 19-23 (2015).

B. R. Betzler, W. R. Martin, B. C. Kiedrowski, and F. B. Brown, “Calculating α Eigenvalues of One-Dimensional Media with Monte Carlo,” Journal of Computational and Theoretical Transport, 43(1-7), pp. 38–49 (2014).

B. R. Betzler, B. C. Kiedrowski, W. R. Martin, et al., "Calculating α Eigenvalue Spectra with Monte Carlo," Proc. ANS Nuclear Criticality Safety Topical Mtg., Wilmington, NC, USA, Sep. 29-Oct. 3 (2013).

A. T. Pavlou, B. R. Betzler, T. P. Burke, J. C. Lee, W. R. Martin, W. N. Pappo, and E. E. Sunny,“Eigenvalue Sensitivity Studies for the Fort St. Vrain High Temperature Gas-Cooled Reactor to Account for Fabrication and Modeling Uncertainties,” Proc. PHYSOR 2012 – Advances in Reactor Physics, Knoxville, TN, USA, Apr. 15–20 (2012).

B. R. Betzler, E. E. Sunny, W. R. Martin, and J. C. Lee, "Coupled Nuclear-Thermal-Hydraulic Calculations for Fort St. Vrain Reactor," Proc. NURETH 14 - The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, Toronto, Ontario, Canada, Sep. 25-30 (2011).

B. R. Betzler, W. R. Martin, and J. C. Lee, "MCNP5 Analysis of the Fort St. Vrain High-Temperature Gas-Cooled Reactor," Trans. Am. Nucl. Soc., 102 (2010).