| Multidimensional multiphysics simulation of nuclear fuel behavior RL Williamson, JD Hales, SR Novascone, MR Tonks, DR Gaston, ... Journal of Nuclear Materials 423 (1-3), 149-163, 2012 | 675 | 2012 |
| BISON theory manual the equations behind nuclear fuel analysis JD Hales, RL Williamson, SR Novascone, G Pastore, BW Spencer, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2016 | 237 | 2016 |
| Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling G Pastore, LP Swiler, JD Hales, SR Novascone, DM Perez, BW Spencer, ... Journal of Nuclear Materials 456, 398-408, 2015 | 180 | 2015 |
| BISON: A flexible code for advanced simulation of the performance of multiple nuclear fuel forms RL Williamson, JD Hales, SR Novascone, G Pastore, KA Gamble, ... Nuclear Technology 207 (7), 954-980, 2021 | 170 | 2021 |
| Multidimensional multiphysics simulation of TRISO particle fuel JD Hales, RL Williamson, SR Novascone, DM Perez, BW Spencer, ... Journal of Nuclear Materials 443 (1-3), 531-543, 2013 | 158 | 2013 |
| 2.0-MOOSE: Enabling massively parallel multiphysics simulation AD Lindsay, DR Gaston, CJ Permann, JM Miller, D Andrš, AE Slaughter, ... SoftwareX 20, 101202, 2022 | 148 | 2022 |
| An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions KA Gamble, T Barani, D Pizzocri, JD Hales, KA Terrani, G Pastore Journal of nuclear materials 491, 55-66, 2017 | 139 | 2017 |
| Validating the BISON fuel performance code to integral LWR experiments RL Williamson, KA Gamble, DM Perez, SR Novascone, G Pastore, ... Nuclear Engineering and Design 301, 232-244, 2016 | 138 | 2016 |
| Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions X Wu, T Kozlowski, JD Hales Annals of Nuclear Energy 85, 763-775, 2015 | 131 | 2015 |
| Verification of the BISON fuel performance code JD Hales, SR Novascone, BW Spencer, RL Williamson, G Pastore, ... Annals of Nuclear Energy 71, 81-90, 2014 | 110 | 2014 |
| A review of fuel performance modelling P Van Uffelen, J Hales, W Li, G Rossiter, R Williamson Journal of Nuclear Materials 516, 373-412, 2019 | 105 | 2019 |
| Modeling and simulation of hydrogen behavior in Zircaloy-4 fuel cladding O Courty, AT Motta, JD Hales Journal of Nuclear Materials 452 (1-3), 311-320, 2014 | 105 | 2014 |
| Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings M Wagih, B Spencer, J Hales, K Shirvan Annals of Nuclear Energy 120, 304-318, 2018 | 104 | 2018 |
| Multiscale modeling of thermal conductivity of high burnup structures in UO2 fuels XM Bai, MR Tonks, Y Zhang, JD Hales Journal of Nuclear Materials 470, 208-215, 2016 | 86 | 2016 |
| Asymptotic expansion homogenization for multiscale nuclear fuel analysis JD Hales, MR Tonks, K Chockalingam, DM Perez, SR Novascone, ... Computational Materials Science 99, 290-297, 2015 | 76 | 2015 |
| TRISO particle fuel performance and failure analysis with BISON W Jiang, JD Hales, BW Spencer, BP Collin, AE Slaughter, SR Novascone, ... Journal of Nuclear Materials 548, 152795, 2021 | 70 | 2021 |
| A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools D Pizzocri, G Pastore, T Barani, A Magni, L Luzzi, P Van Uffelen, SA Pitts, ... Journal of Nuclear Materials 502, 323-330, 2018 | 60 | 2018 |
| Discrete element method for simulation of early-life thermal fracturing behavior in ceramic nuclear fuel pellets H Huang, B Spencer, J Hales Nuclear Engineering and Design 278, 515-528, 2014 | 54 | 2014 |
| Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions T Barani, G Pastore, D Pizzocri, DA Andersson, C Matthews, A Alfonsi, ... Journal of Nuclear Materials 522, 97-110, 2019 | 52 | 2019 |
| Assessment of BISON: A nuclear fuel performance analysis code DM Perez, RL Williamson, SR Novascone, G Pastore, J Hales, ... Idaho National Laboratory, Idaho Falls, 2013 | 48 | 2013 |
Stephen NovasconeComputational Scientist, Idaho National LaboratoryVerified email at inl.gov