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 |
psr-0210 |
SCOPE, Shipping Cask Optimization and Parametric Evaluation |
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 |
ccc-0228 |
SPAR, High-Energy Muon, Pion, Heavy Ion Stopping-Powers and Ranges |
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-1878 |
TRIPOLI-4 version 9S, 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 |