| RMC–A Monte Carlo code for reactor core analysis K Wang, Z Li, D She, Q Xu, Y Qiu, J Yu, J Sun, X Fan, G Yu Annals of Nuclear Energy 82, 121-129, 2015 | 351 | 2015 |
| MCS–A Monte Carlo particle transport code for large-scale power reactor analysis H Lee, W Kim, P Zhang, M Lemaire, A Khassenov, J Yu, Y Jo, J Park, ... Annals of Nuclear Energy 139, 107276, 2020 | 79 | 2020 |
| Development of on-the-fly temperature-dependent cross-sections treatment in RMC code S Liu, Y Yuan, JK Yu, K Wang Annals of Nuclear Energy 94, 144-149, 2016 | 40 | 2016 |
| MCS based neutronics/thermal-hydraulics/fuel-performance coupling with CTF and FRAPCON J Yu, H Lee, M Lemaire, H Kim, P Zhang, D Lee Computer Physics Communications 238, 1-18, 2019 | 38 | 2019 |
| New strategies of sensitivity analysis capabilities in continuous-energy Monte Carlo code RMC Y Qiu, J Liang, K Wang, J Yu Annals of Nuclear Energy 81, 50-61, 2015 | 34 | 2015 |
| Preliminary simulation results of BEAVRS three-dimensional Cycle 1 whole core depletion by UNIST Monte Carlo code MCS H Lee, W Kim, P Zhang, A Khassenov, J Park, J Yu, S Choi, HS Lee, ... | 28 | 2017 |
| Astrophysical factor of the reaction calculated with reduced theory ZD An, ZP Chen, YG Ma, JK Yu, YY Sun, GT Fan, YJ Li, HH Xu, BS Huang, ... Physical Review C 92 (4), 045802, 2015 | 25 | 2015 |
| Preliminary coupling of the Thermal/Hydraulic solvers in the Monte Carlo code MCS for practical LWR analysis J Yu, H Lee, H Kim, P Zhang, D Lee Annals of Nuclear Energy 118, 317-335, 2018 | 20 | 2018 |
| The development and validation of nuclear cross section processing code for reactor-RXSP J Yu, S Li, K Wang, G Wang, G Yu International Conference on Nuclear Engineering 55829, V005T11A005, 2013 | 16 | 2013 |
| Fuel performance analysis of BEAVRS benchmark Cycle 1 depletion with MCS/FRAPCON coupled system J Yu, H Lee, M Lemaire, H Kim, P Zhang, D Lee Annals of Nuclear Energy 138, 107192, 2020 | 14 | 2020 |
| Simulations of BEAVRS benchmark cycle 2 depletion with MCS/CTF coupling system J Yu, H Lee, H Kim, P Zhang, D Lee Nuclear Engineering and Technology 52 (4), 661-673, 2020 | 10 | 2020 |
| Reaction rate tally and depletion calculation with on-the-fly temperature treatment S Liu, Y Yuan, J Yu, K Wang Annals of Nuclear Energy 92, 277-283, 2016 | 10 | 2016 |
| Nuclear data statistical treatment M Alrwashdeh, J Yu, A Abdalla, K Wang ASME. International Conference on Nuclear Engineering 5, V005T11A020, 2013 | 10 | 2013 |
| Verification of depletion capability of OpenMC using VERA depletion benchmark J Yu, B Forget Annals of Nuclear Energy 170, 108973, 2022 | 9 | 2022 |
| Eigenvalue sensitivity and uncertainty analysis based on a 2-D/1-D whole-core transport code KYADJ Q Wu, J Yu, G Shi, X Tang, Y Yu, Q Li, K Wang Annals of Nuclear Energy 122, 185-192, 2018 | 9 | 2018 |
| Practical Monte Carlo simulation using modified power method with preconditioning P Zhang, H Lee, M Lemaire, C Kong, J Choe, J Yu, F Khoshahval, D Lee Annals of Nuclear Energy 127, 372-384, 2019 | 8 | 2019 |
| On-the-fly treatment of temperature dependent cross sections in the unresolved resonance region in RMC code S Liu, Y Yuan, J Yu, D She, K Wang Annals of Nuclear Energy 111, 234-241, 2018 | 8 | 2018 |
| Fuel Performance Coupling of FRAPCON within MCS J Yu, S Lee, D Lee American Nuclear Society, 2017 | 7 | 2017 |
| Preliminary validation of MCS multi-physics coupling capability with CTF J Yu, H Lee, H Kim, P Zhang, D Lee Reactor Physics Asia conference organizer, 2017 | 6 | 2017 |
| Empirical models for multidimensional regression of fission systems AJ Dave, J Yu, J Wilson, B Phillips, K Sun, B Forget arXiv preprint arXiv:2105.14645, 2021 | 5 | 2021 |
