| Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance M Ševeček, A Gurgen, A Seshadri, Y Che, M Wagih, B Phillips, ... Nuclear Engineering and Technology 50 (2), 229-236, 2018 | 163 | 2018 |
| Inverse uncertainty quantification using the modular Bayesian approach based on Gaussian process, Part 1: Theory X Wu, T Kozlowski, H Meidani, K Shirvan Nuclear Engineering and Design 335, 339-355, 2018 | 110 | 2018 |
| On the prediction of critical heat flux using a physics-informed machine learning-aided framework X Zhao, K Shirvan, RK Salko, F Guo Applied Thermal Engineering 164, 114540, 2020 | 100 | 2020 |
| 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 | 98 | 2018 |
| Capital cost estimation for advanced nuclear power plants WR Stewart, K Shirvan Renewable and Sustainable Energy Reviews 155, 111880, 2022 | 58 | 2022 |
| Inverse uncertainty quantification using the modular Bayesian approach based on Gaussian Process, Part 2: Application to TRACE X Wu, T Kozlowski, H Meidani, K Shirvan Nuclear Engineering and Design 335, 417-431, 2018 | 57 | 2018 |
| 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 | 51 | 2021 |
| The design of a compact integral medium size PWR K Shirvan, P Hejzlar, MS Kazimi Nuclear Engineering and Design 243, 393-403, 2012 | 51 | 2012 |
| Physics-informed reinforcement learning optimization of nuclear assembly design MI Radaideh, I Wolverton, J Joseph, JJ Tusar, U Otgonbaatar, N Roy, ... Nuclear Engineering and Design 372, 110966, 2021 | 49 | 2021 |
| Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code Y Che, G Pastore, J Hales, K Shirvan Nuclear Engineering and Design 337, 271-278, 2018 | 42 | 2018 |
| Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response Y Deng, K Shirvan, Y Wu, G Su Journal of Nuclear Materials 507, 24-37, 2018 | 40 | 2018 |
| Multiphysics phase-field modeling of quasi-static cracking in urania ceramic nuclear fuel W Li, K Shirvan Ceramics International 47 (1), 793-810, 2021 | 37 | 2021 |
| Demonstration of the relationship between sensitivity and identifiability for inverse uncertainty quantification X Wu, K Shirvan, T Kozlowski Journal of computational physics 396, 12-30, 2019 | 34 | 2019 |
| Rule-based reinforcement learning methodology to inform evolutionary algorithms for constrained optimization of engineering applications MI Radaideh, K Shirvan Knowledge-Based Systems 217, 106836, 2021 | 33 | 2021 |
| Quenching heat transfer analysis of accident tolerant coated fuel cladding A Seshadri, K Shirvan Nuclear Engineering and Design 338, 5-15, 2018 | 33 | 2018 |
| U3Si2-SiC fuel performance analysis in BISON during normal operation W Li, K Shirvan Annals of Nuclear Energy 132, 34-45, 2019 | 32 | 2019 |
| ABAQUS analysis of the SiC cladding fuel rod behavior under PWR normal operation conditions W Li, K Shirvan Journal of Nuclear Materials 515, 14-27, 2019 | 32 | 2019 |
| Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings A Gurgen, K Shirvan Nuclear Engineering and Design 337, 38-50, 2018 | 31 | 2018 |
| Mechanical performance of SiC three-layer cladding in PWRs VA Avincola, P Guenoun, K Shirvan Nuclear Engineering and Design 310, 280-294, 2016 | 31 | 2016 |
| Three dimensional considerations in thermal-hydraulics of helical cruciform fuel rods for LWR power uprates K Shirvan, MS Kazimi Nuclear Engineering and Design 270, 259-272, 2014 | 29 | 2014 |
