| Nuclide depletion capabilities in the Shift Monte Carlo code GG Davidson, TM Pandya, SR Johnson, TM Evans, AE Isotalo, CA Gentry, ... Annals of Nuclear Energy 114, 259-276, 2018 | 60 | 2018 |
| Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis NR Brown, BR Betzler, JJ Carbajo, AJ Wysocki, MS Greenwood, C Gentry, ... Annals of Nuclear Energy 103, 49-59, 2017 | 50 | 2017 |
| Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification KS Kim, CA Gentry, AT Godfrey, Y Liu, S Palmtag Annals of Nuclear Energy 132, 1-23, 2019 | 22 | 2019 |
| Watts bar unit 2 startup results with vera AT Godfrey, BS Collins, CA Gentry, SG Stimpson, JA Ritchie Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). Consortium for …, 2017 | 21 | 2017 |
| Lattice physics calculations using the embedded self-shielding method in Polaris, Part I: Methods and implementation MA Jessee, WA Wieselquist, U Mertyurek, KS Kim, TM Evans, ... Annals of Nuclear Energy 150, 107830, 2021 | 20 | 2021 |
| Prediction of neutronics parameters within a two-dimensional reflective PWR assembly using deep learning F Shriver, C Gentry, J Watson Nuclear Science and Engineering 195 (6), 626-647, 2021 | 16 | 2021 |
| The NESTLE 3D nodal core simulator: Modern reactor models NP Luciano, KE Ottinger, PE Collins, C Gentry, N George, AJ Pawel, ... ANS MC2015 Joint International Conference on Mathematics and Computation (M …, 2015 | 12 | 2015 |
| Development of molten salt reactor modeling and simulation capabilities in VERA A Graham, B Collins, R Salko Jr, Z Taylor, C Gentry Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2019 | 10 | 2019 |
| Molten salt reactor simulations using MPACT-CTF BS Collins, CA Gentry, AJ Wysocki, RK Salko Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2017 | 9 | 2017 |
| Development of the V4. 2m5 and V5. 0m0 Multigroup Cross Section Libraries for MPACT for PWR and BWR KS Kim, K Clarno, C Gentry, A Godfrey, ML Williams, D Wiarda, ... CASL-U-2017-1280-000, ORNL/TM-2017/95, 2017 | 9 | 2017 |
| AP1000® Benchmarking of VERA Neutronics Toolset C Gentry, AT Godfrey, F Franceschini M&C 2017, 2017 | 9 | 2017 |
| Development of mpact for full-core simulations of MAGNOX gas-cooled nuclear reactors BJ Ade, NP Luciano, AJ Conant, CA Gentry, SG Stimpson, BS Collins, ... EPJ Web of Conferences 247, 06041, 2021 | 8 | 2021 |
| Neutronic Evaluation of a Liquid Salt–Cooled Reactor Assembly C Gentry, GI Maldonado, O Chvala, B Petrovic Nuclear Science and Engineering 187 (2), 166-184, 2017 | 8 | 2017 |
| POLARIS—2D light water reactor lattice physics module MA Jessee, JJ Jarrell, WA Wieselquist, ML Williams, KS Kim, TM Evans, ... Scale Code System; Rearden, BT, Jessee, MA, Eds.; Oak Ridge National …, 2017 | 8 | 2017 |
| A neutronic investigation of the use of fully ceramic microencapsulated fuel for Pu/Np burning in PWRs C Gentry, I Maldonado, A Godfrey, K Terrani, J Gehin, J Powers Nuclear Technology 186 (1), 60-75, 2014 | 8 | 2014 |
| High-Fidelity Ex-Core Capabilities in VERA T Pandya, K Royston, E Davidson, T Evans, A Godfrey, S Henderson, ... EPJ Web of Conferences 247, 06024, 2021 | 7 | 2021 |
| Initial benchmarking of ChemTriton and MPACT MSR modeling capabilities CA Gentry, BR Betzler, BS Collins Transactions of the American Nuclear Society 117, 2017 | 7 | 2017 |
| AP1000 PWR Cycle 1 Hfp Depletion Simulations with Vera-CS D Salazar, F Franceschini, A Petrarca, AT Godfrey, SG Stimpson, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2016 | 7 | 2016 |
| Secondary-Source Core Reload Modeling with VERA C Gentry, B Collins, E Davidson, G Davidson, T Evans, A Godfrey, S Hart, ... Nuclear Science and Engineering 195 (3), 320-337, 2021 | 5 | 2021 |
| Coupled Simulations of Fast-Spectrum Molten Salt Reactors B Collins, A Graham, A Dawn, R Salko, N Smith, C Gentry PHYSOR 2018: Reactor Physics Paving The Way Towards More Efficient Systems …, 2018 | 5 | 2018 |
