Computer Programs

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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 |

nea-1353 | ALBEDO ALBEZ, Gamma and Neutron Attenuation in Air Ducts |

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-0082 | ANISN-JR, 1-D Transport Program ANISN with ZZ JSD Data and Flux Plot |

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 |

ccc-0126 | ASOP, Shield Calculation, 1-D, Discrete Ordinates Transport |

nea-0949 | BERMUDA, 1-D, 2-D, 3-D Neutron and Gamma Transport for Shielding |

ccc-0117 | BETA-2B, Time-Dependent Bremsstrahlung Transport, Electron Transport by Monte-Carlo Method |

nea-0188 | BIGGI-4T, Gamma Transport in Multi-Region Shield in Planar or Spherical Geometry |

psr-0143 | BREESE, Distribution Function for Program MORSE from Albedo Data |

nea-0390 | BRIGITTE, Dose Rate and Heat Source and Energy Flux for Self-Absorbing Rods |

nea-1727 | BULK-I, Radiation Shielding Tool for Proton Accelerator Facilities |

nea-1771 | BULK_C-12, N & photon effective dose rates from medium energy protons or carbon ions through concrete or concrete/iron |

iaea1403 | C-SHIELDER, Gamma shielding calculations of radionuclides emitting photons 0.5 to 10 MeV by different concretes |

nea-1800 | CAFDATS, Converter of Angular Fluxes of DORT, ANISN and TORT Systems |

psr-0131 | CARP, Flux Conversion from Program DOT to Currents for Program BREESE |

psr-0131 | CARP-82, Currents for Program BREESE-2 from ZZ CAD or DOT-4 Flux |

ccc-0024 | CARSTEP, Particle Flux on Space Vehicle in Van Allen Zone |

nesc0742 | CASIM, High Energy Cascades in Shields of Arbitrary Geometry Using Monte-Carlo Method |

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-0070 | CHARGE-2/C, Flux and Dose Behind Shield from Electron, Proton, Heavy Particle Irradiation |

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 |

nea-1126 | COLLI-PTB, Neutron Fluence Spectra for 3-D Collimator System by Monte-Carlo |

nea-0383 | COSANI-2, Gamma Doses from SABINE Calculation, Activity from ANISN Flux Calculation |

nea-0247 | CYGAS, 3-D Gamma Flux in Axial or Cylindrical Shields from Cylindrical Source |

nea-0494 | CYLDOS, Dose Rate in Cylindrical Shield from Cylindrical Source |

ccc-0366 | DASH, Void Tracing Sn and Monte-Carlo Coupling Program with Angular Fluxes from DOT Program |

nea-1603 | DCHAIN-SP 2001, Code System for Analyzing Decay and Build-up Characteristics of Spallation Products |

ccc-0520 | DCTDOS, Neutron and Gamma Penetration in Composite Duct System |

nesc0754 | DEMONR, Monte-Carlo Shielding Calculation for Neutron Flux and Neutron Spectra, Teaching Program |

nea-0667 | DIFFAX, Axial Streaming for Hexagonal Lattices in Gas Cooled FBR, Slab Geometry Diffusion |

nea-0625 | DINE, Neutron Flux, Neutron Dose Rate in Multi-Region Slab Reactor Shield by Removal Diffusion |

nea-0391 | DLS, 2-D Diffusion with Line-of-Sight Method for Cavities |

psr-0155 | DOGS, Flux Plots of Radiation Transport Program Using DISSPLA |

psr-0064 | DOMINO, Coupling of Discrete Ordinate Program DOT with Monte-Carlo Program MORSE |

ccc-0650 | DOORS, 1-,2-,3-dimensional discrete-ordinates system for deep-penetration neutron and photon transport |

ccc-0543 | DORT, 1-D 2-D Discrete Ordinate Neutron and Photon Transport with Deep Penetration |

ccc-0532 | DORT-PC, 2-D Discrete Ordinates Transport System |

nea-1711 | DORTDAT2, Input-Making Support System for a Two-Dimensional SN Code, DORT |

iaea0922 | DOSKMF2, Dose Rate Distribution in Co60 Gamma Irradiation Plants |

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 |

psr-0251 | DSNQUAD, Angular Quadrature Weights and Cosines for ANISN |

nea-1671 | DUCT-III, Design Code for Duct-Streaming Radiations |

ccc-0453 | DUST, Albedo Monte-Carlo Simulation of Neutron Streaming in Multilegged Square Concrete Ducts |

nea-1813 | EASYQAD 2.0, 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 |

ccc-0119 | ELBA, Bremsstrahlung Dose from Isotropic Electron Flux on Plane Al Shield |

ccc-0301 | ELPHO, Muon, Electron, Positron Generator from Pions by Monte-Carlo with HETC Collision Data |

nea-1683 | ERANOS 2.3, 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 |

ccc-0351 | FALSTF, Neutron Flux and Gamma Flux Detector Response Outside Cylindrical Shields |

nea-0566 | FEM-RZ, 2-D MultiGroup Neutron Transport in R-Z Geometry, Eigenvalue and Fixed Source Problems |

nea-1833 | FLUKA2011.2c.3, Monte Carlo general purpose tool for calculations of particle transport and interactions with matter |

nea-0596 | FOCUS, Neutron Transport System for Complex Geometry Reactor Core and Shielding Problems by Monte-Carlo |

iaea1388 | FOTELP-2014, Photons, Electrons and Positrons Transport in 3D by Monte Carlo Techniques |

nea-1846 | FSKY4C, Gamma Ray Skyshine Analysis Code |

ccc-0494 | G33-GP, Multigroup Gamma Scattering Using Geometric Progression Buildup Factors |

nea-1175 | GAMFIL, Photon Production Cross-Sections in ENDF/B Format |

ccc-0042 | GAMLEG-JR, MultiGroup Gamma Cross-Sections, Energy Absorption Coefficient Generator for Transport Calculation |

nea-0268 | GAMMONE, Multi-Region Shield Gamma Penetration from Various Geometries Source by Monte-Carlo |

nea-0584 | GFX/GAMP1, Above-Ground Radiation Field from Terrestrial K, U, Th Gamma Emitters |

nesc0045 | GRACE GRACE-1, MultiGroup Multi-Region Gamma Attenuation Gamma Dose in Slab Geometry |

nesc0046 | GRACE-2, MultiGroup Multi-Region Gamma Attenuation Gamma Dose in Cylindrical or Spherical Geometry |

nea-1690 | GRTUNCL-3D/R-THETA-Z, Code to Calculate Semi Analytic First Collision Source and Uncollided Flux in an R-theta-Z grid |

ccc-0721 | GRTUNCL3D, Code to Calculate Semi Analytic First Collision Source and Uncollided Flux (X, Y, Z) |

ccc-0276 | GRUNCLE, 1st Collision Source Calculation for Program DOT |

ccc-0697 | GUI2QAD, Graphical Interface for QAD-CGPIC, Point Kernel for Shielding Calculations |

nea-1265 | HERMES-KFA, High-Energy Radiation Transport by Monte-Carlo |

ccc-0651 | ICOM, Ion Radiation Transport Calculation for Shielding and Dosimetry |

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, TIGER System of Coupled Electron Photon Transport by Monte-Carlo |

ccc-0696 | LAHET 2.8, Code System for High Energy Particle Transport Calculations |

psr-0020 | LAPHAN0, P0 Gamma Production Matrices from ENDF/B |

nea-0124 | LGH, Gamma Streaming and Neutron Streaming for Duct |

ccc-0064 | LPSC, Protons and Neutron Flux, Spectra Behind Slab Shield from Protons Irradiation |

nea-1306 | LSHINSE, Air Scattering Neutron and Gamma Doserates for Complex Shielding Geometry |

ccc-0220 | LUIN-II, Cosmic Ray Cascade Generator and Particle Fluxes |

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-1747 | MONTE-CARLO-WS-2005, Proceedings of Monte Carlo Criticality Calculations & TRIPOLI-IV Workshops 2005 |

ccc-0127 | MORSE, MultiGroup Neutron Transport and Gamma Transport for Complex Geometry Shields by Monte-Carlo |

ccc-0431 | MORSE-C, Neutron Transport, Gamma Transport for Criticality Calculation by Monte-Carlo Method |

ccc-0474 | MORSE-CGA, Monte-Carlo Neutron and Gamma MultiGroup Transport with Array Geometry |

nea-1181 | MORSE-DD, Monte-Carlo Neutron Transport with Combinatorial Geometry Using DDL Cross-Sections Library |

ccc-0127 | MORSE-E, Program MORSE with Uniform Source for Various Geometry |

ccc-0588 | MORSE-EMP, Monte-Carlo Neutron and Gamma MultiGroup Transport with Array Geometry, for PC |

nea-1673 | MVP/GMVP II, MC Codes for Neutron & Photon Transport Calc. based on Continuous Energy and Multigroup Methods |

ccc-0164 | NAC, Neutron Activation Analysis and Isotope Inventory |

ccc-0462 | NCRP49, X-Ray Shielding for Radiographic and Fluoroscopic Diagnostic Units |

psr-0355 | NJOY-94, General ENDF/B Processing System for Reactor Design Problems |

psr-0171 | NJOY91, General ENDF/B Processing System for Reactor Design Problems |

nea-0125 | NRN, Removal-Diffusion for Squares and Cylindrical Geometry with Energy Transfer Matrix |

ccc-0046 | OGRE, Monte-Carlo System for Gamma Transport Problems |

psr-0275 | ORMONTE, Uncertainty Analysis for User-Developed System Models |

nea-1008 | PALLAS-1D(VII), Direct Integration of Transport Equation in 1-D Planar and Spherical Geometry |

nea-0702 | PALLAS-2DY, 2-D Neutron Transport, Gamma Transport with Anisotropic Scattering for Fixed Source |

ccc-0760 | PARTISN 5.97, 1-D, 2-D, 3-D Time-Dependent, Multigroup Deterministic Parallel Neutral Particle Transport Code |

nea-1238 | PASC-1, Petten AMPX-II/SCALE-3 Code System for Reactor Neutronics Calculation |

iaea0855 | PELSHIE, Dose Rates from Gamma Source by Point-Kernel Integration |

nea-1525 | PENELOPE2014, A Code System for Monte-Carlo Simulation of Electron and Photon Transport |

nea-1886 | PENGEOM, tools for handling complex quadric geometries in Monte Carlo simulations of radiation transport |

nea-1339 | PEPIN, Methodology for Computing Concentrations, Activities, Gamma-Ray Spectra, and Residual Heat from Fission Products. |

nea-1857 | PHITS-2.88, Particle and Heavy Ion Transport code System |

ccc-0160 | PICA, Photon-Induced Medium-Range Nuclear Cascade Analysis by Monte-Carlo |

psr-0238 | PICTURE, 2-D Slices Through 3-D CG of MORSE, QAD-CG |

nea-0416 | PIPE, 1-D Gamma Transport for Slab, Spherical Shields with Compton Scattering Calculation |

iaea1172 | PKI, Gamma Radiation Reactor Shielding Calculation by Point-Kernel Method |

ccc-0381 | PLACID, Gamma Streaming in Cylindrical Duct Shields by Monte-Carlo |

iaea0905 | PRESTO, Slab Shields for Time-Dependent Gamma Spectra |

ccc-0618 | PTRAN, Proton Transport for 50 to 250 MeV by Monte-Carlo |

ccc-0595 | PUTZ, Point-Kernel 3-D Gamma Shielding |

nea-1679 | PVIS-4, Pressure vessel irradiation, source preparation |

ccc-0493 | QAD-CGGP, Fast Neutron and Gamma Penetration in Shields with Combinatorial Geometry |

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 |

ccc-0083 | RAID, Gamma, Neutron Scattering into Cylindrical or Multibend Duct |

nea-0519 | REDIFFUSION, 1-D Neutron Removal-Diffusion and Gamma Point-Kernel Calculation for Shielding |

psr-0482 | REMIT5.1, Radiation exposure monitoring and information transmittal system |

nea-0598 | RSYST, Modular System for Reactor Core and Shielding Problems |

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-0187 | SAM-CE, Time-Dependent 3-D Neutron Transport, Gamma Transport in Complex Geometry by Monte-Carlo |

iaea0837 | SAMSY, Neutron and Gamma Dose Rates and Heat Source for Multilayer Shields |

ccc-0361 | SANDYL, 3-D Time-Dependent and Space-Dependent Gamma Electron Cascade Transport by Monte-Carlo |

ccc-0834 | SCALE 6.2.1, A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design |

ccc-0418 | SCAP-82, Single Scattering, Albedo Scattering, Point-Kernel Analysis in Complex Geometry |

psr-0210 | SCOPE, Shipping Cask Optimization and Parametric Evaluation |

nea-0407 | SCORE-4, 2-D Removal Diffusion in X-Y or R-Z Geometry for Rectangular Shields |

ccc-0729 | SERA-1C1, Simulation environment for radiotherapy applications |

iaea0841 | SFAK, Unscattered Gamma Self-Absorption from Regular Fuel Rod Assemblies |

nea-1239 | SFERXS, Photoabsorption, Coherent, Incoherent Scattering Cross-Sections Function for Shielding |

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-0379 | SHIELDOSE, Doses from Electron and Proton Irradiation in Space Vehicle Al Shields |

nea-0466 | SHREDI, Neutron Flux and Neutron Activation in 2-D Shields by Removal Diffusion |

ccc-0289 | SKYSHINE, Dose Rate Outside Concrete Steel Building from 6 MeV Gamma by Monte-Carlo |

nea-1046 | SMART, Radiation Dose Rates on Cask Surface |

ccc-0120 | SPACETRAN, Radiation Leakage from Cylinder with ANISN Flux Calculation |

ccc-0228 | SPAR, High-Energy Muon, Pion, Heavy Ion Stopping-Powers and Ranges |

ccc-0148 | SPARES, Program System for Space Radiation Environment and Shielding System Evaluation |

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 |

ccc-0460 | SPOT1, Gamma-Ray Dose Rate from Cylindrical Source Volume |

nea-0919 | SRIM-2008, Stopping Power and Range of Ions in Matter |

iaea1382 | SRNA-2K5, Proton Transport Using 3-D by Monte Carlo Techniques |

psr-0330 | STARCODES, Stopping Power and Ranges for Electrons, Protons, He |

iaea0970 | STOPOW, Stopping Power of Fast Ions in Matter |

ccc-0067 | STORM, Radiation Hazard of Solar Flares for Space Vehicles |

psr-0282 | SUPERDAN-PC, Dancoff Factor for Spherical, Cylindrical, Slab Geometry |

iaea1437 | SUPERMC, Super Monte Carlo simulation program for nuclear and radiation process |

ccc-0248 | SWAN-PPL, Fusion Reactor 1-D Particle Transport Optimization |

ccc-0638 | TART2016, 3D Coupled Neutron-Photon Combinatorial Geometry, Time Dependent, Monte Carlo Transport Code |

nea-0619 | TIMOC-ESP, Time-Dependent Response Function by Monte-Carlo with Interface to Program TIMOC-72 |

ccc-0759 | TITAN 1.29, A Three-Dimensional Deterministic Radiation Transport Code System |

ccc-0543 | TORT, 2-D 3-D Discrete Ordinate Neutron and Photon Transport with Deep Penetration |

nea-0668 | TRD-3, In-Core and Out-Core Neutron Flux, Gamma Flux by 2-D Removal Diffusion in Cylindrical Geometry |

iaea0833 | TREEDE, Point Fluxes and Currents Based on Track Rotation Estimator by Monte-Carlo Method |

nea-1716 | TRIPOLI-4 version 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 |

ccc-0537 | TRIPOS, Monte Carlo Ion Transport Analysis Code |

nea-1086 | TRISTAN, 3-D fixed source radiation transport |

ccc-0547 | TWODANT-SYS, DANTSYS3.0, 1-D, 2-D, 3-D MultiGroup Discrete Ordinate Method Transport |

ccc-0195 | TWOTRAN-GG-FC, General Geometry 2-D Transport with 1st Collision Source Calculation |

ccc-0195 | TWOTRAN-GG-VW, General Geometry 2-D Transport, Variable-Weight Diamond Difference |

iaea1434 | U-SHIELDER, Estimates Shielding Thickness of Depleted Uranium for Photons from 0.5 to 10 MeV |

psr-0281 | URR, Cross-Sections, Selfshielding for Fertile and Fissile Isotopes in Unresolved Region |

ccc-0262 | VCS, Radiation Protection Factors in Vehicles by Monte-Carlo |

nea-1856 | VESTA 2.1.5, 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 |

ccc-0525 | XRAY-AAC, X-Ray Attenuation and Absorption |

nea-1251 | ZYLIND, Gamma Penetration for Cylindrical Source and Shield Geometry |

dlc-0049 | ZZ AIRFEWG, Gamma, Neutron Transport Calculation in Air Using FEWG1 Cross-Section |

nea-0886 | ZZ AMPX-2/123, 123-Group Neutron Cross-Section Library from ENDF/B-4 by AMPX-2 |

nea-0886 | ZZ AMPX-2/219, 219-Group Neutron Cross-Section Library from ENDF/B-4 by AMPX-2 |

dlc-0027 | ZZ AMPX01/27C, Coupled Neutron-Gamma Group Constant Library by AMPX for Transport Calculation |

dlc-0129 | ZZ ANS643, Geometric Progression Gamma-Ray Buildup Factor Coefficient Library |

nea-0673 | ZZ BABEL, Multigroup Neutron Cross-Section Data Library for Fast Reactor Shield Calculation |

iaea1237 | ZZ BARC-75, Coupled 50 Neutron-Group 25 Gamma-Group Cross-Section Library for 42 Nuclides |

dlc-0008 | ZZ BP-3, 104-Group Neutron Cross-Section Library for Transport Calculation |

dlc-0008 | ZZ BP-6, 104 Group Neutron and Gamma-Ray Multigroup Cross-Section Library for Transport Calculation |

iaea0949 | ZZ BROND, Evaluated Neutron Data Library in ENDF-6 Format |

nea-1872 | ZZ BUGENDF70.BOLIB, ENDF/B-VII.0 Broad-Group Coupled X Sect. Lib. for LWR Shielding & Pressure Vessel Dosimetry Applic. |

nea-1866 | ZZ BUGJEFF311.BOLIB, JEFF-3.1.1 Broad-Group Coupled X Sect Lib. for LWR Shielding & Pressure Vessel Dosimetry Applic. |

dlc-0185 | ZZ BUGLE-96, Multigroup Coupled Neutron Gamma Cross-Section for LWR Shielding Calculation |

dlc-0059 | ZZ CAD, 51 Neutron-Group, 25 Gamma-Group Albedo Data for 4 Materials from DOT Flux |

dlc-0130 | ZZ DABL69, 46-Group Neutron, 23-Group Gamma Cross-Section in ANISN Format from ENDF/B-V |

nea-0791 | ZZ DAMSIG84, 640-Group Damage Cross-Section Library for SAND-2 Calculation |

nea-1538 | ZZ DECNET-GENDF, Fusion Damage Library of 175 Neutron and 42 Photon VITAMIN-J Groups |

dlc-0012 | ZZ DLC-12D POPLIB, Secondary Gamma Yields and Cross-Section Library for POPOP-4 Calculation |

dlc-0013 | ZZ DLC-13B, Resonance Cross-Section Group Constant Library for Tungsten and Depleted Pu |

dlc-0015 | ZZ DLC-15 STORM-ISRAEL, Gamma Interaction Cross-Section Library in ENDF/B Format for Transport |

dlc-0021 | ZZ DLC-21, X-Ray Attenuation Cross-Section Library from 0.1 KeV to 1 MeV |

dlc-0023 | ZZ DLC-23F CASK, 40-Group Neutron and Gamma Coupled Cross-Section for PWR Shipping Casks |

dlc-0031 | ZZ DLC-31, 37 Neutron-Group, 21 Gamma-Group Coupled Group Constants Library from ENDF/B |

dlc-0103 | ZZ ENDL86, Evaluated Charged Particle, Neutron, Photon Cross-Section Library |

nea-0794 | ZZ EURLIB, Coupled Neutron Gamma Multigroup Cross-Section Library from ENDF/B for Shielding Calculations |

dlc-0085 | ZZ FCXSEC, Coupled Cross-Section Library for Shielding from VITAMIN-C in AMPX, ANISN Format |

iaea0964 | ZZ FGXRRS, 10 Neutron-Group, 7 Gamma-Group Self-Shielded Cross-Section in ANISN Format |

nea-1544 | ZZ GEFF-2-MATXS, Coupled Neutron-Gamma Fusion Neutronics Library in MATXS Format |

nea-1102 | ZZ GEFF1, 175-Group Neutron Cross-Section in VITAMIN-J1 Format for Shielding Benchmarks |

dlc-0220 | ZZ HILO2K, Coupled 83 Neutron, 22 Photon Group Cross Sections for Neutron Energies Up to 2 GeV for ANISN, DORT and TORT |

dlc-0119 | ZZ HILO86, 66 Neutron, 22 Gamma Group Cross-Section Library for ANISN, DORT, MORSE |

dlc-0187 | ZZ HILO86R, 66 Neutron, 22 Gamma Group Cross-Section for 400 MeV Neutron, 20 MeV Gamma |

dlc-0007 | ZZ HPICE/F, Gamma Interaction Cross-Section Library in ENDF/B Format for Transport Calculation |

dlc-0099 | ZZ HUGO, Photon Interaction Data Library in ENDF-5 Format |

dlc-0160 | ZZ KAOS/LIB-V, Kerma Factors, Nuclear Response Function Library for Fission, Fusion |

iaea0870 | ZZ L26P3S34, 26-Group Constants Library of 34 Materials for Neutron Shielding Calculations |

dlc-0128 | ZZ LAHIMACK, Multigroup Neutron and Gamma Cross-Section and Response Function up to 800 MeV |

dlc-0029 | ZZ MACKLIB, Nuclear Response Function Library for CTR and Hybrid Fission Fusion System Materials |

dlc-0060 | ZZ MACKLIB-4, 171-Neutron, 36-Gamma Group Response Function Library from ENDF/B-IV |

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 |

nea-1205 | ZZ MATX175/42-JEFF87, 172 Neutron-Group, 42 Gamma-Group MATXS Library in VITAMIN-J Structure |

dlc-0176 | ZZ MATXS10, 30-Group Neutron, 12-Group Gamma Cross-Sections in MATXS Format from ENDF/B-VI |

dlc-0200 | ZZ MCNPDATA, ZZ-MCB-DLC200, Standard Neutron, Photon and Electron Data Libraries for MCNP-4C and MCB1C |

dlc-0033 | ZZ MONTAGE-400, Neutron Activation 100-Group Cross-Section Library of Fusion Reactor Materials |

iaea1217 | ZZ N-SPECT/DET-RESP, Neutron Spectra and Detector Responses for Radiation Protection |

dlc-0172 | ZZ NUCDECAY, Nuclear Decay Data for Radiation Dosimetry Calculation for ICRP and MIRD |

dlc-0136 | ZZ PHOTX, Photon Interaction Cross-Section Library for 100 Elements |

dlc-0126 | ZZ PVE, 38-Group P8 Photon Cross-Section Library for Gamma Radiation Transport |

nea-1545 | ZZ RFL-2-DTF, Group Constant Library of Reaction Cross-Section, Gas Production, KERMA, DPA |

dlc-0057 | ZZ SAIL, Albedo Scattering Data Library for 3-D Monte-Carlo Radiation Transport in LWR Pressure Vessel |

dlc-0045 | ZZ SENPRO/45C, Multigroup Sensitivity Library for Fast Reactors, Thermal Reactors |

dlc-0139 | ZZ SIGMA-A, Photon Interaction and Absorption Cross-Section Library |

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-0113 | ZZ VITAMIN-E, 174-Group Neutron, 38-Group Gamma Cross-Section in AMPX Format |

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. |

dlc-0026 | ZZ WM-NRSM, Neutron and Gamma Group Cross-Section Library for Nuclear Rocket Shielding Calculations |

dlc-0174 | ZZ XCOM, Photon Cross-Section Library for Personal Computer |

nea-1891 | ZZ-VITJEFF32.BOLIB, JEFF-3.2 Multi-Grp Coupled (199n+ 42gamma) X-Sec. Lib. in AMPX Fmt for Nuclear Fission Applications |