| nea-1839 | ACAB-2008, ACtivation ABacus Code |
| iaea1432 | AL-SHIELDER, calculates shielding thickness of aluminum for any photon emitting radionuclide between 0.5 to 10 MeV |
| psr-0315 | AMPX-77, Modular System for Coupled Neutron-Gamma MultiGroup Cross-Sections from ENDF/B-5 |
| ccc-0082 | ANISN-E, 1-D Transport Program ANISN with Exponential Model |
| nea-0363 | ANISN-FONTENAY, 1-D Planar, Spherical, Cylindrical Neutron Transport and Gamma Transport with Deep Penetration |
| ccc-0254 | ANISN-ORNL, 1-D Neutron Transport & Gamma Transport in Slab, Cylindrical, Spherical Geometry with Anisotropic Scattering |
| ccc-0255 | ANISN-W, 1-D Transport Calculation for Deep Penetration Problems |
| ccc-0514 | ANISN/PC, MultiGroup 1-D Discrete Ordinates Transport with Anisotropic Scattering |
| nea-0949 | BERMUDA, 1-D, 2-D, 3-D Neutron and Gamma Transport for Shielding |
| nea-1727 | BULK-I, Radiation Shielding Tool for Proton Accelerator Facilities |
| iaea1403 | C-SHIELDER, Gamma shielding calculations of radionuclides emitting photons 0.5 to 10 MeV by different concretes |
| psr-0262 | CASKCODES, Program CAPSIZE Scope KWIKDOSE for Shipping Cask Shielding |
| ccc-0544 | CEPXS ONELD, 1-D Coupled Electron Photon MultiGroup System |
| ccc-0837 | CEPXS, Coupled Electron-Photon Cross Section |
| ccc-0726 | CNCSN 2009, One, Two- and Three-Dimensional Coupled Neutral and Charged Particle Sn Parallel Multi-Threaded Code System |
| ccc-0829 | COG11.1, Multiparticle Monte Carlo Code System for Shielding and Criticality Use |
| ccc-0547 | DANTSYS3.0, 1-D, 2-D, 3-D MultiGroup Discrete Ordinate Method Transport |
| nea-1603 | DCHAIN-SP 2001, Code System for Analyzing Decay and Build-up Characteristics of Spallation Products |
| nea-0391 | DLS, 2-D Diffusion with Line-of-Sight Method for Cavities |
| ccc-0650 | DOORS3.2A, 1-,2-,3-dimensional discrete-ordinates system for deep-penetration neutron and photon transport |
| ccc-0532 | DORT-PC, 2-D Discrete Ordinates Transport System |
| nea-1711 | DORTDAT2, Input-Making Support System for a Two-Dimensional SN Code, DORT |
| ccc-0276 | DOT-3.5, 2-D Neutron Transport, Gamma Transport Program DOT with New Space-Scaling |
| ccc-0320 | DOT-4.2, 2-D Neutron Transport, Gamma Transport with Space Dependent Mesh and Quadrature |
| nea-1671 | DUCT-III, Design Code for Duct-Streaming Radiations |
| ccc-0744 | EASYQAD 2.0.1, Visualization for Gamma and Neutron Shielding Calculations |
| nea-0969 | EDMULT-6.4, Electron Depth Dose Distribution in Multilayer Slab Absorbers |
| ccc-0331 | EGS4, Electron Photon Shower Simulation by Monte-Carlo |
| nea-1683 | ERANOS 2.3N, Modular code and data system for fast reactor neutronics analyses |
| ccc-0107 | ETRAN, Electron Transport and Gamma Transport with Secondary Radiation in Slab by Monte-Carlo |
| nesc9578 | FACET, Radiation View Factor with Shadowing |
| iaea1438 | FE-SHIELDER, shielding thickness of Iron for any photon emitting radionuclide between 0.5 and 10 MeV |
| nea-1833 | FLUKA2011.2X.4, Monte Carlo general purpose tool for calculations of particle transport and interactions with matter |
| iaea1388 | FOTELP-2018, Photons, Electrons and Positrons Transport in 3D by Monte Carlo Techniques |
| nea-1846 | FSKY4C, Gamma Ray Skyshine Analysis Code |
| ccc-0721 | GRTUNCL3D, Code to Calculate Semi Analytic First Collision Source and Uncollided Flux (X, Y, Z) |
| ccc-0697 | GUI2QAD, Graphical Interface for QAD-CGPIC, Point Kernel for Shielding Calculations |
| ccc-0636 | ISO-PC, X-Ray, Gamma-Bremsstrahlung Dose-Rates |
| ccc-0079 | ISOSHLD, Decay Gamma Dose, Bremsstrahlung Dose Behind Shield, Fission Products Source Strength |
| ccc-0467 | ITS-3.0, Integrated TIGER Series of Coupled Electron-Photon Monte Carlo Codes. |
| ccc-0696 | LAHET 2.8, Code System for High Energy Particle Transport Calculations |
| nea-0124 | LGH, Gamma Streaming and Neutron Streaming for Duct |
| nea-1047 | MANYCASK, Radiation Dose Rate Around Many Casks |
| nea-1307 | MARMER, Point-Kernel Shielding Calculation with Nuclide Concentrations from ORIGEN-S |
| nea-1643 | MCB1C, Monte-Carlo Continuous Energy Burnup Code |
| nea-1733 | MCNP4B-GN, Monte Carlo Code System for (gamma,n) production and transport in high-Z materials |
| ests1678 | MCSLTT, Monte Carlo Simulation of Light Transport in Tissue |
| nea-1166 | MCVIEW, 3-D Radiation View Factor by Monte-Carlo Method |
| nea-0351 | MERCURE, 3-D Gamma Heating and Gamma Dose Rate and Fast Flux by Monte-Carlo |
| nea-0194 | MERCURE-3, Gamma Attenuation by Line-of-Flight in 3-D Heterogeneous Geometry |
| nea-1673 | MVP/GMVP V.3, MC Codes for Neutron & Photon Transport Calc. based on Continuous Energy and Multigroup Methods |
| psr-0275 | ORMONTE, Uncertainty Analysis for User-Developed System Models |
| ccc-0760 | PARTISN 5.97, 1-D, 2-D, 3-D Time-Dependent, Multigroup Deterministic Parallel Neutral Particle Transport Code |
| ccc-0842 | PARTISN 8.29, Time-Dependent, Parallel Neutral Particle Transport Code System |
| iaea0855 | PELSHIE-PC, Dose Rates from Gamma Source by Point-Kernel Integration |
| nea-1525 | PENELOPE2023, A Code System for Monte-Carlo Simulation of Electron and Photon Transport |
| nea-1339 | PEPIN, Methodology for Computing Concentrations, Activities, Gamma-Ray Spectra, and Residual Heat from Fission Products. |
| nea-1931 | PHITS-3.X, Particle and Heavy Ion Transport code System |
| nea-0416 | PIPE, 1-D Gamma Transport for Slab, Spherical Shields with Compton Scattering Calculation |
| ccc-0618 | PTRAN, Proton Transport for 50 to 250 MeV by Monte-Carlo |
| nea-1679 | PVIS-4, Pressure vessel irradiation, source preparation |
| ccc-0645 | QAD-CGGP-A, Fast Neutron, Gamma Penetration in Shields with Combinatorial Geometry |
| ccc-0396 | QADMOD-G, Point-Kernel Gamma-Ray Shielding Program |
| ccc-0617 | QBF, Radiation Dose Distribution Around Spent Fuel Shipping Casks |
| nea-0467 | RADHEAT, Transport, Heat Generator, Radiation Damage Cross-Sections in Reactor and Shield |
| psr-0482 | REMIT5.1, Radiation exposure monitoring and information transmittal system |
| nea-0402 | SABINE-3, Neutron Penetration and Gamma Penetration in Reactor Shield for Planar, Spherical, Cylindrical Geometry |
| nea-1884 | SACALC-ELLIPSOID, Calculates the average solid angle subtended by a ellipsoid solid or surface |
| nea-1688 | SACALC3, Calculates the average solid angle subtended by a volume |
| ccc-0361 | SANDYL, 3-D Time-Dependent and Space-Dependent Gamma Electron Cascade Transport by Monte-Carlo |
| ccc-0729 | SERA-1C1, Simulation environment for radiotherapy applications |
| iaea1287 | SHIELD, Monte-Carlo Code for Simulating Interaction of High Energy Hadrons with Complex Macroscopic Targets |
| iaea1391 | SHIELDER, Gamma shielding calculations of radionuclides emitting photons 0-5 to 10 MeV |
| ccc-0289 | SKYSHINE2&3-SKYIII-PC, Dose Rate Outside Concrete Steel Building from 6 MeV Gamma by Monte-Carlo |
| nea-1046 | SMART, Radiation Dose Rates on Cask Surface |
| nea-0468 | SPARK, Time-Dependent 1-D, 2-D, 3-D Diffusion with Heat Transfer and Feedback |
| psr-0263 | SPECTER-ANL, Neutron Damage for Material Irradiation |
| nea-0919 | SRIM-2008, Stopping Power and Range of Ions in Matter |
| iaea1382 | SRNA-2020, Proton Transport Using 3-D by Monte Carlo Techniques |
| psr-0330 | STARCODES, Stopping Power and Ranges for Electrons, Protons, He |
| iaea0970 | STOPOW88, Stopping Power of Fast Ions in Matter |
| iaea1437 | SUPERMC 3.3.0, Super Monte Carlo simulation program for nuclear and radiation process |
| ccc-0638 | TART2022, 3D Coupled Neutron-Photon Combinatorial Geometry, Time Dependent, Monte Carlo Transport Code |
| ccc-0759 | TITAN 1.29, A Three-Dimensional Deterministic Radiation Transport Code System |
| ccc-0543 | TORT-DORT, 1-D 2-D 3-D Discrete Ordinate Neutron and Photon Transport with Deep Penetration |
| nea-1716 | TRIPOLI-4 VERS. 8.1, 3D general purpose continuous energy Monte Carlo Transport code |
| nea-1940 | TRIPOLI-4.12, Coupled Neutron, Photon, Electron, Positron 3-D, Time Dependent Monte-Carlo Transport Calculation |
| nea-1086 | TRISTAN, 3-D fixed source radiation transport |
| iaea1434 | U-SHIELDER, Estimates Shielding Thickness of Depleted Uranium for Photons from 0.5 to 10 MeV |
| nea-1856 | VESTA 2.1&AURORA1.0, Monte Carlo depletion interface code and AURORA 1.0.0, Depletion analysis tool |
| ccc-0754 | VIM 5.1, Steady-State 3-D Neutron Transport Using ENDF/B or Multigroup Cross Sections |
| iaea1417 | W-SHIELDER, calculates shielding thickness of water for photon emitting radionuclide between 0.5 to 10 MeV |
| nea-1251 | ZYLIND, Gamma Penetration for Cylindrical Source and Shield Geometry |
| nea-1740 | ZZ MATJEF22.BOLIB, JEF-2.2 Multigr Coupled (199n + 42gamma) X-Section Lib. in MATXS Fmt for Nuclear Fission Applications |
| nea-1847 | ZZ MATJEFF31.BOLIB, JEFF-3.1 Multigr Coupled(199n + 42gamma) X-Section Lib.in MATXS Fmt for Nuclear Fission Applications |
| iaea1217 | ZZ N-SPECT/DET-RESP, Neutron Spectra and Detector Responses for Radiation Protection |
| dlc-0136 | ZZ PHOTX, Photon Interaction Cross-Section Library for 100 Elements |
| dlc-0256 | ZZ VIP-MAN, Computational Phantom |
| dlc-0184 | ZZ VITAMIN-B6, Fine-Group Cross-Section Library from ENDF/B-VI.3 for Radiation Transport |
| dlc-0245 | ZZ VITAMINB7/BUGLEB7, Broad-Grp, Fine-Grp, Coupled N/Gamma Cross-Sec Lib derived from ENDF/B-VII.0 Nuclear Data |
| nea-1870 | ZZ VITENDF70.BOLIB, ENDF/B-VII.0 Multi-Grp Coupled (199n +42gamma)X-Sec.Lib.in AMPX Fmt for Nuclear Fission Applications |
| nea-1699 | ZZ VITJEF22.BOLIB, JEF-2.2 Multigr Coupled (199n + 42gamma) X-Section Lib. in AMPX Fmt for Nuclear Fission Applications |
| nea-1801 | ZZ VITJEFF31.BOLIB,JEFF-3.1 Multigr Coupled (199n + 42gamma) X-Section Lib. in AMPX Fmt for Nuclear Fission Applications |
| nea-1869 | ZZ VITJEFF311.BOLIB, JEFF-3.1.1 Multi-Group Coupled (199n + 42gamma) X-Sec Lib in AMPX Fmt for Nuclear Fission Applic. |
| nea-1891 | ZZ VITJEFF32.BOLIB, JEFF-3.2 Multi-Grp Coupled (199n+ 42gamma) X-Sec. Lib. In AMPX Fmt for Nuclear Fission Applications |
