Jiankai Yu

RMC – A Monte Carlo code for reactor core analysis

Kan Wang, Zeguang Li, Ding She et al. · Annals of Nuclear Energy · 2014 · 354 citations

Engineering, Nuclear Engineering, Physics +14

MCS – A Monte Carlo particle transport code for large-scale power reactor analysis

Hyunsuk Lee, Wonkyeong Kim, Peng Zhang et al. · Annals of Nuclear Energy · 2020 · 76 citations

Engineering, Nuclear Engineering, Physics +12

Development of on-the-fly temperature-dependent cross-sections treatment in RMC code

Shichang Liu, Yuan Yuan, Jiankai Yu et al. · Annals of Nuclear Energy · 2016 · 42 citations

Engineering, Nuclear Engineering, Heat Transfer +6

New strategies of sensitivity analysis capabilities in continuous-energy Monte Carlo code RMC

Yishu Qiu, Jingang Liang, Kan Wang et al. · Annals of Nuclear Energy · 2015 · 33 citations

Computing, Computational Engineering, Nuclear Engineering +14

MCS based neutronics/thermal-hydraulics/fuel-performance coupling with CTF and FRAPCON

Jiankai Yu, Hyunsuk Lee, Matthieu Lemaire et al. · Computer Physics Communications · 2019 · 33 citations · Full text

Engineering, Nuclear Engineering, Heat Transfer +9