C. Gentry

Two-Step Procedure for Liquid-Salt-Cooled-Reactor Analysis

G. I. Maldonado, K. Kim, C. Gentry, 2018, Nuclear Technology.

Secondary-Source Core Reload Modeling with VERA

William A. Wieselquist, Benjamin Collins, Kang Seog Kim, 2020 .

Nuclide depletion capabilities in the Shift Monte Carlo code

Seth R. Johnson, A. Isotalo, W. Wieselquist, 2018 .

Lattice physics calculations using the embedded self-shielding method in Polaris, Part I: Methods and implementation

K. Kim, M. Jessee, W. Wieselquist, 2021 .

HIGH-FIDELITY EX-CORE CAPABILITIES IN VERA

Tara M. Pandya, Benjamin Collins, Shane Stimpson, 2021, EPJ Web of Conferences.

Prediction of Neutronics Parameters Within a Two-Dimensional Reflective PWR Assembly Using Deep Learning

C. Gentry, F. Shriver, Justin Watson, 2021, Nuclear Science and Engineering.

Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis

Nicholas R. Brown, Aaron J. Wysocki, Benjamin R. Betzler, 2017 .

An Investigation of the use of Ceramic Microencapsulated Fuel for Transuranic Waste Recycling in Pressurized Water Reactors

C. Gentry, 2012 .