(UNIST), Republic of Korea. Mercury - A LLNL developed Monte Carlo particle transport code. MONK - A Monte Carlo Code for criticality safety and reactor physics analyses developed and supported by the ANSWERS Software Service. MORET - Monte-Carlo code for the evaluation of criticality risk in nuclear installations developed at IRSN, France OpenMC - An open source, community-developed open source Monte Carlo code RMC - A Tsinghua University -Department of Engineering Physics developed Monte Carlo code for general radiation transport Serpent - A VTT Technical Research Centre of Finland developed Monte Carlo particle transport code Shift/KENO - ORNL developed Monte Carlo codes for general radiation transport and criticality analysis TRIPOLI - 3D general purpose continuous energy Monte Carlo Transport code developed at CEA, France Deterministic codes Ardra - A LLNL neutral particle transport code Attila - A commercial transport code DRAGON - An open-source lattice physics code PHOENIX/ANC - A proprietary lattice-physics and global diffusion code suite from Westinghouse Electric PARTISN - A LANL developed transport code based on the discrete ordinates method NEWT - An ORNL developed 2-D SN code DIF3D/VARIANT - An Argonne National Laboratory developed 3-D code originally developed for fast reactors DENOVO - A massively parallel transport code under development by ORNL Jaguar - A parallel 3-D Slice Balance Approach transport code for arbitrary polytope grids developed at NNL DANTSYS RAMA - A proprietary 3D method of characteristics code with arbitrary geometry modeling, developed for EPRI by TransWare Enterprises Inc. RAPTOR-M3G - A proprietary parallel radiation transport code developed by Westinghouse Electric Company OpenMOC - An MIT developed open source parallel method of characteristics code MPACT - A parallel 3D method of characteristics code under development by Oak Ridge National Laboratory and the University of Michigan DORT - Discrete Ordinates Transport APOLLO - A lattice physics code used by CEA, EDF and Areva CASMO - Lattice physics code developed by Studsvik for LWR analysis milonga - A free nuclear reactor core analysis code STREAM - A neutron transport analysis code, STREAM (Steady state and Transient REactor Analysis code with Method of Characteristics), has been developed since 2013 at Ulsan National Institute of Science and Technology (UNIST), Republic of Korea See also Nuclear reactor Boltzmann equation TINTE Neutron scattering Monte Carlo N-Particle Transport Code References Lewis, E., & Miller, W. (1993). Computational Methods of Neutron Transport. American Nuclear Society. . Duderstadt, J., & Hamilton, L. (1976). Nuclear