# List of software for nuclear engineering

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

* Geant4 (CERN)
* McCARD (KAIST)
* MCNP (LANL)
* 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-0315 | AMPX-77, Modular System for Coupled Neutron-Gamma MultiGroup Cross-Sections from ENDF/B-5 |
| ccc-0459 | BOLD/VENTURE-4, Reactor Analysis System with Sensitivity and Burnup |
| nesc0387 | CITATION, 3-D MultiGroup Diffusion with 1st Order Perturbation and Criticality Search |
| ccc-0643 | CITATION-LDI2, 2-D MultiGroup Diffusion, Perturbation, Criticality Search, for PC |
| ccc-0650 | DOORS3.2A, 1-,2-,3-dimensional discrete-ordinates system for deep-penetration neutron and photon transport |
| uscd1234 | DRAGON 3.05D, Reactor Cell Calculation System with Burnup |
| nesc0784 | DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plant |
| nea-1683 | ERANOS 2.3N, Modular code and data system for fast reactor neutronics analyses |
| nea-1916 | FINPSA TRAINING 2.2.0.1 -R-, a PSA model in consisting of event trees, fault trees, and cut sets |
| nea-0624 | JOSHUA, Neutronics, Hydraulics, Burnup, Refuelling of LWR |
| psr-0608 | SAPHIRE 8.0.9, Systems Analysis Programs for Hands-On Integrated Reliability Evaluations |
| iaea1439 | STACY, Very High Temp. Reactor V/HTR Safety Analyses for the Quantification of Fission Product Release from the Fuel |
| iaea1437 | SUPERMC 3.3.0, Super Monte Carlo simulation program for nuclear and radiation process |
| iaea1370 | TRIGLAV, Research Reactor Calculations |
| uscd1239 | VENTEASY, Criticality Search for a Desired Keffective by Adjusting Dimensions, Nuclide Concentrations, or Buckling |
| ccc-0654 | VENTURE-PC 1.1, Reactor Analysis System with Sensitivity and Burnup |
| iaea0871 | VPI-NECM, Nuclear Engineering Program Collection for College Training |
| nea-0655 | VSOP, Neutron Spectra, 2-D Flux Synthesis, Fuel Management, Thermohydraulics Calculation |
| iaea1440 | VSOP99-11, Neutron Spectra, 2-D Flux Synthesis, Fuel Management, Thermohydraulics Calculation |

### Particle Accelerators and High Voltage Machines

| nesc0983 | EGUN, Charged Particle Trajectories in Electromagnetic Focusing System |
| ests0428 | POISSON SUPERFISH, Poisson Equation Solver for Radio Frequency Cavity |
| ccc-0228 | SPAR, High-Energy Muon, Pion, Heavy Ion Stopping-Powers and Ranges |

### Magnetic Fusion Research

| nea-1839 | ACAB-2008, ACtivation ABacus Code |
| nea-1638 | ANITA-IEAF, Isotope Inventories from Intermediate Energy Neutron Irradiation for Fusion Applications |
| nesc0873 | COAST-4, Design and Cost of Tokamak Fusion Reactors |
| nea-1200 | ELEORBIT, 3-D Simulation of Electron Orbits in Magnetic Multipole Plasma Source |
| nea-0490 | HEDO-2, Magnetic Field Calculation and Plot of Air Core Coils |
| nea-0583 | MEDUSA-PIJ, 1-D Thermohydraulic Analysis of Laser Driven Plasma |
| ccc-0858 | TMAP7, 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 (ORNL)
* MPACT (ORNL)
* 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
* 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