RMC – A Monte Carlo code for reactor core analysis

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

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

Development of burnup methods and capabilities in Monte Carlo code RMC

Ding She, Yuxuan Liu, Kan Wang et al. · Annals of Nuclear Energy · 2012 · 59 citations

Computing, Computer Science, Computational Physics +9

MONTE CARLO TECHNIQUE TO SOLVE. THE STATIC EIGENVALUE PROBLEM OF THE BOLTZMANN TRANSPORT EQUATION.

J. Lieberoth · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1968 · 56 citations

Engineering, Physics, Computational Physics +10