OpenMC: A state-of-the-art Monte Carlo code for research and development

The OpenMC Monte Carlo particle transport code

Paul Romano, Benoit Forget · Annals of Nuclear Energy · 2012 · 463 citations · Full text

Natural Sciences, Physics, Computational Physics +9

The Probability Table Method for Treating Unresolved Neutron Resonances in Monte Carlo Calculations

L.B. Levitt · Nuclear Science and Engineering · 1972 · 118 citations

Natural Sciences, Nuclear Engineering, Physics +17

Benchmark for evaluation and validation of reactor simulations (BEAVRS)

Nicholas E. Horelik, Bryan Herman, Benoit Forget et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2013 · 115 citations

Engineering, Computational Engineering, Nuclear Engineering +17

Two practical methods for unionized energy grid construction in continuous-energy Monte Carlo neutron transport calculation

Jaakko Leppänen · Annals of Nuclear Energy · 2009 · 77 citations

Engineering, Nuclear Engineering, Physics +14

Direct Doppler broadening in Monte Carlo simulations using the multipole representation

Benoit Forget, Sheng Xu, Kord Smith · Annals of Nuclear Energy · 2013 · 56 citations · Full text

Natural Sciences, Physics, Computational Physics +11