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.[1] The codes can be separated by use and function. Most of the software are written in C and Fortran.[2]
| 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 |
| 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 |
| 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 |
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