| Coupled neutronic thermo-hydraulic analysis of full PWR core with Monte-Carlo based BGCore system D Kotlyar, Y Shaposhnik, E Fridman, E Shwageraus Nuclear Engineering and Design 241 (9), 3777-3786, 2011 | 86 | 2011 |
| The stochastic implicit Euler method–A stable coupling scheme for Monte Carlo burnup calculations J Dufek, D Kotlyar, E Shwageraus Annals of Nuclear Energy 60, 295-300, 2013 | 73 | 2013 |
| Numerical stability of the predictor–corrector method in Monte Carlo burnup calculations of critical reactors J Dufek, D Kotlyar, E Shwageraus, J Leppänen Annals of Nuclear Energy 56, 34-38, 2013 | 69 | 2013 |
| On the use of predictor–corrector method for coupled Monte Carlo burnup codes D Kotlyar, E Shwageraus Annals of Nuclear Energy 58, 228-237, 2013 | 58 | 2013 |
| Numerically stable Monte Carlo-burnup-thermal hydraulic coupling schemes D Kotlyar, E Shwageraus Annals of Nuclear Energy 63, 371-381, 2014 | 43 | 2014 |
| serpentTools: A python package for expediting analysis with serpent AE Johnson, D Kotlyar, S Terlizzi, G Ridley Nuclear Science and Engineering 194 (11), 1016-1024, 2020 | 38 | 2020 |
| Weighted-delta-tracking for Monte Carlo particle transport LWG Morgan, D Kotlyar Annals of Nuclear Energy 85, 1184-1188, 2015 | 31 | 2015 |
| Low enriched nuclear thermal propulsion neutronic, thermal hydraulic, and system design space analysis M Krecicki, D Kotlyar Nuclear Engineering and Design 363, 110605, 2020 | 27 | 2020 |
| Axial discontinuity factors for the nodal diffusion analysis of high conversion BWR cores E Fridman, S Duerigen, Y Bilodid, D Kotlyar, E Shwageraus Annals of Nuclear Energy 62, 129-136, 2013 | 25 | 2013 |
| Low-enriched cermet-based fuel options for a nuclear thermal propulsion engine JT Gates, A Denig, R Ahmed, VK Mehta, D Kotlyar Nuclear Engineering and Design 331, 313-330, 2018 | 23 | 2018 |
| Stochastic semi-implicit substep method for coupled depletion Monte-Carlo codes D Kotlyar, E Shwageraus Annals of Nuclear Energy 92, 52-60, 2016 | 22 | 2016 |
| Developments within the WIMS reactor physics code for whole core calculations B Lindley, G Hosking, P Smith, D Powney, B Tollit, T Fry, R Perry, T Ware, ... Proceedings of the International Conference on Mathematics and Computational …, 2017 | 20 | 2017 |
| Evaluation of Yttrium Hydride (δ-YH2-x) Thermal Neutron Scattering Laws and Thermophysical Properties VK Mehta, MWD Cooper, RB Wilkerson, D Kotlyar, DV Rao, SC Vogel Nuclear Science and Engineering 195 (6), 563-577, 2021 | 19 | 2021 |
| A density functional theory and neutron diffraction study of the ambient condition properties of sub-stoichiometric yttrium hydride VK Mehta, SC Vogel, AP Shivprasad, EP Luther, DA Andersson, DV Rao, ... Journal of Nuclear Materials 547, 152837, 2021 | 19 | 2021 |
| Selection of a space reactor moderator using lessons learned from SNAP and ANP programs VK Mehta, P McClure, D Kotlyar AIAA Propulsion and Energy 2019 Forum, 4451, 2019 | 19 | 2019 |
| Hybrid microscopic depletion model in nodal code DYN3D Y Bilodid, D Kotlyar, E Shwageraus, E Fridman, S Kliem Annals of Nuclear Energy 92, 397-406, 2016 | 18 | 2016 |
| Fission matrix decomposition method for criticality calculations: Theory and proof of concept S Terlizzi, D Kotlyar Nuclear Science and Engineering, 2019 | 17 | 2019 |
| Full-core coupled neutronic, thermal-hydraulic, and thermo-mechanical analysis of low-enriched uranium nuclear thermal propulsion reactors M Krecicki, D Kotlyar Energies 15 (19), 7007, 2022 | 15 | 2022 |
| High-resolution thermal analysis of nuclear thermal propulsion fuel element using OpenFOAM JC Wang, D Kotlyar Nuclear Engineering and Design 372, 110957, 2021 | 15 | 2021 |
| Capturing multiphysics effects in hydride moderated microreactors using MARM VK Mehta, J Armstrong, DV Rao, D Kotlyar Annals of Nuclear Energy 172, 109067, 2022 | 13 | 2022 |
Eugene ShwagerausUniversity of CambridgeDirección de correo verificada de cam.ac.uk