Results 131 to 140 of about 538 (156)
Some of the next articles are maybe not open access.
Verification of depletion capability of OpenMC using VERA depletion benchmark
Annals of Nuclear Energy, 2022Jiankai Yu, Benoit Forget
exaly
Benchmarking and verification of the OpenMC code for accelerator-based neutron source analyses
Fusion Engineering and Design, 2021Yuan Hu, Yuefeng Qiu, Yudong Lu
exaly
Integration of OpenMC methods into MAMMOTH and Serpent
2016Leslie Kerby, Mark DeHart, Aaron Tumulak
openaire +1 more source
Extension and benchmarking of the OpenMC code for accelerator-based neutron source applications
Fusion Engineering and Design, 2020Yuan Hu, Yuefeng Qiu
exaly
Implementation and Validation of Photon Transport in OpenMC
2018Amanda Lund, Paul Romano
openaire +1 more source
Implementation and benchmarking of an automatic global variance reduction method on OpenMC
Fusion Engineering and Design, 2021Yuan Hu, Sha Yan, Yuefeng Qiu
exaly
Evaluation of Openmc Calculations Coupling with Phits, Fluka, and Geant4 for Ads Study
SSRN Electronic Journal, 2022Neng Pu +5 more
openaire +1 more source
OpenMC: A state-of-the-art Monte Carlo code for research and development
Annals of Nuclear Energy, 2015Paul K Romano +2 more
exaly