| nea-1839 | ACAB-2008, ACtivation ABacus Code |
| nea-1942 | ANICCA, Advanced Nuclear Inventory Cycle Code for fuel cycle scenario analysis |
| nea-1638 | ANITA-IEAF, Isotope Inventories from Intermediate Energy Neutron Irradiation for Fusion Applications |
| ccc-0657 | BETA-S 6, Multi-Group Beta-Ray Spectra |
| nea-1735 | CARL 2.3, radiotoxicity, activity, dose and decay power calculations for spent fuel |
| ests1071 | CECP(BWR) CECP(PWR), Decommissioning Costs for PWR and BWR |
| ccc-0544 | CEPXS ONELD, 1-D Coupled Electron Photon MultiGroup System |
| ccc-0837 | CEPXS, Coupled Electron-Photon Cross Section |
| ccc-0604 | CHAINS-PC, Decay Chain Atomic Densities |
| ccc-0755 | CINDER 1.05, Actinide Transmutation Calculations Code |
| nesc0313 | CINDER, Depletion and Decay Chain Calculation for Fission Products in Thermal Reactors |
| 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 |
| psr-0614 | COBRA-SFS 6.0, Thermal-Hydraulic Analysis of Multi-Assembly Spent Fuel Storage and Transportation Systems |
| ests0135 | COBRA-SFS CYCLE3, Thermal Hydraulic Analysis of Spent Fuel Casks |
| iaea1226 | CORD-2, PWR Core Design and Fuel Management |
| ccc-0640 | DCHAIN, Isotope Buildup and Isotope Decay by 1 Point Approximation |
| nea-1603 | DCHAIN-SP 2001, Code System for Analyzing Decay and Build-up Characteristics of Spallation Products |
| nea-1887 | DESAE, develop prospective nuclear energy scenarios in a regional and global scale |
| psr-0531 | EEDB, The Energy Economic Data Base |
| nea-1683 | ERANOS 2.3N, Modular code and data system for fast reactor neutronics analyses |
| nea-0617 | FAPMAN-IC, LWR Fuel Cost Analysis with Program ORSIM Interface |
| nea-0706 | FISPIN, Isotope Buildup and Isotope Decay for Actinides, Fission Products, Structure Materials |
| nesc0576 | GEM-NESC, Fuel Cycle Cost and Economics for Thermal Reactor, Present Worth Analysis |
| nea-1935 | HRP-LEGACY-DB, Halden Reactor Project Legacy Database |
| nea-0288 | KERBREK, Fuel Cycle Cost Analysis for Power Reactor |
| nea-1001 | KORIGEN, Isotope Inventory, Radiation Heat from PWR Burnup |
| nea-0441 | KPD, Time-Dependent Fuel Cycle Cost Calculation for Various Reactor Types |
| ccc-0631 | LWRARC-1.0, PWR and BWR Spent Fuel Decay Heat Generator |
| nea-1643 | MCB1C, Monte-Carlo Continuous Energy Burnup Code |
| psr-0455 | MONTEBURNS 2.0, An Automated, Multi-Step Monte Carlo Burnup Code System |
| nea-1845 | MURE v2 - SMURE, MCNP Utility for Reactor Evolution: couples Monte-Carlo transport with fuel burnup calculations |
| iaea1411 | NAAPRO, Neutron Activation Analysis Prognosis and Optimization code |
| nea-1324 | OREST, LWR Burnup Simulation Using Program HAMMER and ORIGEN |
| ccc-0371 | ORIGEN-2.2, Isotope Generation and Depletion Code Matrix Exponential Method |
| ccc-0702 | ORIGEN-ARP 2.00, Isotope Generation and Depletion Code System-Matrix Exponential Method with GUI and Graphics Capability |
| nea-0622 | ORIGEN-JR, Radiation Source and Nuclide Transmutation with In-Core Burnup |
| nea-1880 | ORIP-XXI, isotope transmutation simulations |
| nea-1339 | PEPIN, Methodology for Computing Concentrations, Activities, Gamma-Ray Spectra, and Residual Heat from Fission Products. |
| nea-1929 | POSY, Power system model for system costs evaluation |
| ccc-0708 | REBUS-PC 1.4, Code System for Analysis of Research Reactor Fuel Cycles |
| ccc-0653 | REBUS3/VARIANT8.0, Code System for Analysis of Fast Reactor Fuel Cycles |
| nesc1065 | REFCO83, Nuclear Fuel Cycle Cost Economics Using Discounted Cash Flow Analysis |
| nea-1231 | REFREP, Near-Field Model for Spent Fuel Repository |
| nea-1840 | SERPENT 1.1.7, 3-D continuous-energy Monte Carlo reactor physics burnup calculation, lattice physics applications |
| nea-1923 | SERPENT V2.2.X, 3-D continuous-energy Monte Carlo reactor physics burnup calculation, lattice physics applications |
| nea-1767 | SMAFS, Steady-state analysis Model for Advanced Fuelcycle Schemes |
| nea-0450 | SOTHIS, PWR Fuel Cycle Equilibrium Cost Evaluation |
| nea-1151 | SUSD, Sensitivity and Uncertainty in Neutron Transport and Detector Response |
| nea-1628 | SUSD3D, 1-, 2-, 3-Dimensional Cross Section Sensitivity and Uncertainty Code |
| iaea1214 | TRIGAC, Flux and Power Distribution and Burnup for TRIGA Reactor |
| nea-1856 | VESTA 2.1&AURORA1.0, Monte Carlo depletion interface code and AURORA 1.0.0, Depletion analysis tool |
| 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 |
| nea-1882 | XSUN-2023, Windows interface environment for transport and sensitivity-uncertainty software TRANSX-2, PARTISN and SUSD3D |
