With the decreased cost and increased capabilities of computers, Nuclear Engineering has implemented computer software (Computer code to Mathematical model) into all facets of this field. There are a wide variety of fields associated with nuclear engineering, but computers and associated software are used most often in design and analysis. Neutron kinetics, thermal-hydraulics, and structural mechanics are all important in this effort. Each software needs to be tested and verified before use. The codes can be separated by use and function. Most of the software are written in C and Fortran.
Monte Carlo Radiation Transport COG (LLNL) Geant4 (CERN) McCARD (KAIST) MCNP (LANL) MCU (MCU) (Kurchatov Institute) OpenMC PHITS (JAEA) SCALE (KENO V and KENO VI) (ORNL) Serpent (VTT) TRIPOLI-4 (CEA)
Transmutation, fuel depletion
ACAB code Activation and transmutation calculations for nuclear applications ORIP_XXI code Isotope transmutation simulations ORILL Code 1D transmutation, fuel depletion (burn-up) and radiological protection code FISPACT-II Multiphysics, inventory and source-term code MURE Serpent-MCNP utility for Reactor Evolution VESTA Monte Carlo depletion interface code
Reactor Systems Analysis psr-0315AMPX-77, Modular System for Coupled Neutron-Gamma MultiGroup Cross-Sections from ENDF/B-5ccc-0459BOLD/VENTURE-4, Reactor Analysis System with Sensitivity and Burnupnesc0387CITATION, 3-D MultiGroup Diffusion with 1st Order Perturbation and Criticality Searchccc-0643CITATION-LDI2, 2-D MultiGroup Diffusion, Perturbation, Criticality Search, for PCccc-0650DOORS3.2A, 1-,2-,3-dimensional discrete-ordinates system for deep-penetration neutron and photon transportuscd1234DRAGON 3.05D, Reactor Cell Calculation System with Burnupnesc0784DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plantnea-1683ERANOS 2.3N, Modular code and data system for fast reactor neutronics analysesnea-1916FINPSA TRAINING 2.2.0.1 -R-, a PSA model in consisting of event trees, fault trees, and cut setsnea-0624JOSHUA, Neutronics, Hydraulics, Burnup, Refuelling of LWRpsr-0608SAPHIRE 8.0.9, Systems Analysis Programs for Hands-On Integrated Reliability Evaluationsiaea1439STACY, Very High Temp. Reactor V/HTR Safety Analyses for the Quantification of Fission Product Release from the Fueliaea1437SUPERMC 3.3.0, Super Monte Carlo simulation program for nuclear and radiation processiaea1370TRIGLAV, Research Reactor Calculationsuscd1239VENTEASY, Criticality Search for a Desired Keffective by Adjusting Dimensions, Nuclide Concentrations, or Bucklingccc-0654VENTURE-PC 1.1, Reactor Analysis System with Sensitivity and Burnupiaea0871VPI-NECM, Nuclear Engineering Program Collection for College Trainingnea-0655VSOP, Neutron Spectra, 2-D Flux Synthesis, Fuel Management, Thermohydraulics Calculationiaea1440VSOP99-11, Neutron Spectra, 2-D Flux Synthesis, Fuel Management, Thermohydraulics Calculation
Particle Accelerators and High Voltage Machines nesc0983EGUN, Charged Particle Trajectories in Electromagnetic Focusing Systemests0428POISSON SUPERFISH, Poisson Equation Solver for Radio Frequency Cavityccc-0228SPAR, High-Energy Muon, Pion, Heavy Ion Stopping-Powers and Ranges
Magnetic Fusion Research nea-1839ACAB-2008, ACtivation ABacus Codenea-1638ANITA-IEAF, Isotope Inventories from Intermediate Energy Neutron Irradiation for Fusion Applicationsnesc0873COAST-4, Design and Cost of Tokamak Fusion Reactorsnea-1200ELEORBIT, 3-D Simulation of Electron Orbits in Magnetic Multipole Plasma Sourcenea-0490HEDO-2, Magnetic Field Calculation and Plot of Air Core Coilsnea-0583MEDUSA-PIJ, 1-D Thermohydraulic Analysis of Laser Driven Plasmaccc-0858TMAP7, Tritium Migration Analysis Program
Toolkit
PyNE The Nuclear Engineering Toolkit
Nuclear Fuel Cycle
Cyclus An agent-based framework for modeling the flow of material through nuclear fuel cycles.
Deterministic Radiation Transport
CASMO5 (Studsvik) HELIOS-2 (Studsvik) SCALE (Oak Ridge National Laboratory) MPACT (Oak Ridge National Laboratory) THOR nTRACER (Seoul National University)
Steady-state Reactor Analysis
SIMULATE5
Spatial Kinetics
PARCS SIMULATE-3K NESTLE
Thermal-Hydraulics ATHLET (GRS, Gesellschaft für Anlagen- und Reaktorsicherheit) TRACE (NRC) SPACE (KEPCO) RELAP5-3D (Idaho National Laboratory) GOTHIC (Numerical Advisory Solutions) CATHARE (CEA) FLICA-4 (CEA) RETRAN (RETRAN-02 and RETRAN-3D) VIPRE-01 PROTO-FLO PROTO-HX PROTO-HVAC PROTO-Sprinkler
Computational Fluid Dynamics
CFX (ANSYS) FLUENT (ANSYS) StarCD (Siemens) STAR-CCM+ (Siemens) LOGOS COBRA-TF GOTHIC TransAT code_saturne (EDF) neptune_cfd (EDF) Trio_CFD (CEA)
Severe Accident
ATHLET-CD (GRS) MELCOR (Sandia National Laboratories) MAAP (EPRI) ASTEC (IRSN and GRS)
Many codes are supported by the U.S. Nuclear Regulatory Commission (NRC). These include SCALE, PARCS, TRACE (Formerly RELAP5 and TRAC-B), MELCOR, and many others.
http://www.nrc.gov/about-nrc/regulatory/research/safetycodes.html
See also Safety code (nuclear reactor) Computational science Computational physics Computer simulation List of computational physics software List of plasma physics software List of software for nanostructures modeling
References
External links http://www.min.uc.edu/nuclear/current_research/sinema-research/codes-of-interest https://www.nrc.gov/about-nrc/regulatory/research/safetycodes.html http://www.oecd-nea.org/tools/abstract/list http://www.ne.anl.gov/codes/ http://www.irsn.fr/EN/Research/Scientific-tools/Computer-codes/Pages/Computer-codes-2624.aspx https://www.oecd-nea.org/tools/abstract/list/category/*