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 | 152 | 2021 |
2.0-MOOSE: Enabling massively parallel multiphysics simulation AD Lindsay, DR Gaston, CJ Permann, JM Miller, D Andrš, AE Slaughter, ... SoftwareX 20, 101202, 2022 | 105 | 2022 |
Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: A critical review C Matthews, C Unal, J Galloway, DD Keiser Jr, SL Hayes Nuclear Technology 198 (3), 231-259, 2017 | 98 | 2017 |
Cluster dynamics simulation of uranium self-diffusion during irradiation in UO2 C Matthews, R Perriot, MWD Cooper, CR Stanek, DA Andersson Journal of Nuclear Materials 527, 151787, 2019 | 59 | 2019 |
Coupled multiphysics simulations of heat pipe microreactors using DireWolf C Matthews, V Laboure, M DeHart, J Hansel, D Andrs, Y Wang, J Ortensi, ... Nuclear Technology 207 (7), 1142-1162, 2021 | 55 | 2021 |
Fission gas diffusion and release for Cr2O3-doped UO2: From the atomic to the engineering scale MWD Cooper, G Pastore, Y Che, C Matthews, A Forslund, CR Stanek, ... Journal of Nuclear Materials 545, 152590, 2021 | 52 | 2021 |
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 | 47 | 2019 |
Cluster dynamics simulation of xenon diffusion during irradiation in UO2 C Matthews, R Perriot, MWD Cooper, CR Stanek, DA Andersson Journal of Nuclear Materials 540, 152326, 2020 | 45 | 2020 |
Atomistic modeling of out-of-pile xenon diffusion by vacancy clusters in UO2 R Perriot, C Matthews, MWD Cooper, BP Uberuaga, CR Stanek, ... Journal of Nuclear Materials 520, 96-109, 2019 | 39 | 2019 |
Automatic differentiation in MetaPhysicL and its applications in MOOSE A Lindsay, R Stogner, D Gaston, D Schwen, C Matthews, W Jiang, ... Nuclear Technology 207 (7), 905-922, 2021 | 38 | 2021 |
A CALPHAD-informed approach to modeling constituent redistribution in Zr-based metallic fuels using BISON J Hirschhorn, M Tonks, C Matthews Journal of Nuclear Materials 544, 152657, 2021 | 16 | 2021 |
Irradiation-enhanced diffusion and diffusion-limited creep in U3Si2 MWD Cooper, KA Gamble, L Capolungo, C Matthews, DA Andersson, ... Journal of Nuclear Materials 555, 153129, 2021 | 13 | 2021 |
Metallic fuel cladding degradation model development and evaluation for BISON Y Miao, A Oaks, K Mo, M Billone, C Matthews, AX Zabriskie, S Novascone, ... Nuclear Engineering and Design 385, 111531, 2021 | 12 | 2021 |
Radiation re-solution of fission gas in non-oxide nuclear fuel C Matthews, D Schwen, AC Klein Journal of Nuclear Materials 457, 273-278, 2015 | 12 | 2015 |
Empirical and mechanistic transient fission gas release model for high-burnup LOCA conditions N Capps, L Aagesen, D Andersson, O Baldwin, WC Brinkley, ... Journal of Nuclear Materials 584, 154557, 2023 | 11 | 2023 |
Phase-field simulations of fission gas bubbles in high burnup UO2 during steady-state and LOCA transient conditions LK Aagesen, S Biswas, W Jiang, D Andersson, MWD Cooper, C Matthews Journal of Nuclear Materials 557, 153267, 2021 | 11 | 2021 |
Atomistic and cluster dynamics modeling of fission gas (Xe) diffusivity in TRISO fuel kernels XY Liu, C Matthews, W Jiang, MWD Cooper, JD Hales, DA Andersson Journal of Nuclear Materials 561, 153539, 2022 | 9 | 2022 |
Preliminary Applications of NEAMS Codes for Multiphysics Modeling of a Heat Pipe Microreactor NE Stauff, K Mo, Y Cao, JW Thomas, Y Miao, C Lee, C Matthews, B Feng proceedings of ANS Annual 2021 meeting, 2021 | 9 | 2021 |
Metal Hydride Simulations Using SWIFT C Matthews, AP Shivprasad, MWD Cooper Los Alamos National Lab.(LANL), Los Alamos, NM (United States), 2021 | 8 | 2021 |
Improvement of the BISON U3Si2 modeling capabilities based on multiscale developments to modeling fission gas behavior KA Gamble, G Pastore, MWD Cooper, DA Andersson, C Matthews, ... Journal of Nuclear Materials 555, 153097, 2021 | 8 | 2021 |