Matthieu Lemaire

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 · 73 citations

Engineering, Nuclear Physics, Monte Carlo +13

Validation of UNIST Monte Carlo code MCS for criticality safety analysis of PWR spent fuel pool and storage cask

Jaerim Jang, Wonkyeong Kim, Sanggeol Jeong et al. · Annals of Nuclear Energy · 2018 · 39 citations

Safety Engineering, Safety-critical System, Engineering +12

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, Thermal Hydraulics +4

Core design of long‐cycle small modular lead‐cooled fast reactor

Tung Dong Cao Nguyen, Jiwon Choe, Bamidele Ebiwonjumi et al. · International Journal of Energy Research · 2018 · 23 citations · Full text

Engineering, Liquid Metal Cooling, Energy Efficiency +16

For a better estimation of gamma heating in nuclear material-testing reactors and associated devices: status and work plan from calculation methods to nuclear data

Matthieu Lemaire, Claire Vaglio-Gaudard, A. Lyoussi et al. · Journal of Nuclear Science and Technology · 2015 · 19 citations · Full text

Engineering, Gamma Heating, Bias Determination +16