| nea-1250 | 2D-SEEP - 3D-SEEP, 2-3-D Ground Water Flow in Permeable Geologic Media |
| nea-1732 | 3D-TRANS-2003, Workshop on Common Tools and Interfaces for Radiation Transport Codes |
| psr-0248 | ABAREX, Optical Statistical Model Neutron Cross-Sections Using ABACUS and NEARREX |
| nea-1839 | ACAB-2008, ACtivation ABacus Code |
| nea-0976 | ACCULIB, Program Library of Mathematical Routines |
| nea-1072 | ACFA, Isotope Activation of Coolant and Structure Materials |
| iaea0960 | ACTIV-JINR, Experimental Gamma Spectra Unfolding |
| nea-1708 | ADEFTA 4.1, Atomic Densities for Transport Analysis |
| ccc-0831 | ADVANTG 3.0.3, AutomateD VAriaNce reducTion Generator |
| ccc-0854 | ADVANTG 3.2.1, AutomateD VAriaNce reducTion Generator without ORNL-TN |
| nea-1913 | AEROSOL-SCIENCE, Aerosol Science: Theory and Practice with Special Applications to the Nuclear Industry |
| nea-0001 | AIREK-MOD, Time Dependent Reactor Kinetics with Feedback Differential Equation |
| iaea1274 | AIREKMOD-RR, Reactivity Transients in Nuclear Research Reactors |
| nea-1130 | AIRGAMMA, External Gamma-Ray Exposure from Radioactive Cloud |
| nesc0326 | AIROS-2A, Space-Independent Reactor Kinetics and Space-Dependent Heat Transfer, Mass Transfer |
| iaea1432 | AL-SHIELDER, calculates shielding thickness of aluminum for any photon emitting radionuclide between 0.5 to 10 MeV |
| uscd1238 | ALICE2011, Particle Spectra from HMS precompound Nucleus Decay |
| ccc-0612 | ALPHN, (Alpha, N) Neutron Production in High-Level Waste Canisters |
| nea-0403 | AMARA, Correlation of Nuclear Data to Integral Experiment by Lagrange Multipliers |
| iaea1251 | AMICO, Cross-Sections Data for ANISN, DOT from WIMS Library |
| ccc-0793 | AMP, Advanced Multi-Physics |
| psr-0315 | AMPX-77, Modular System for Coupled Neutron-Gamma MultiGroup Cross-Sections from ENDF/B-5 |
| uscd0795 | AMRAW, Risk Assessment Method for Radioactive Waste Management |
| nea-1235 | AND, Atomic Number Densities for Criticality Calculation |
| nea-1798 | ANGELO-LAMBDA, Covariance matrix interpolation and mathematical verification |
| 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-1638 | ANITA-IEAF, Isotope Inventories from Intermediate Energy Neutron Irradiation for Fusion Applications |
| nea-1657 | ANL-BPB, Argonne National Laboratory Code Center Benchmark Problem Book |
| ests1169 | ARCON96, Radioactive Plume Concentration in Reactor Control Rooms |
| nea-1581 | ART MOD2, Fission Product Migration in Primary System and Containment |
| ccc-0417 | AT123D, 1-D, 2-D, 3-D Transient Waste Transport Simulation in Groundwater |
| ccc-0179 | ATR, Radiation Transport Models in Atmosphere at Various Altitudes |
| nea-0949 | BERMUDA, 1-D, 2-D, 3-D Neutron and Gamma Transport for Shielding |
| ccc-0657 | BETA-S 6, Multi-Group Beta-Ray Spectra |
| nea-0683 | BLOK, Turbulent Flow in Pipes and Channels with Rectangular Obstruction |
| ccc-0459 | BOLD/VENTURE-4, Reactor Analysis System with Sensitivity and Burnup |
| nea-1678 | BOT3P5.4, 3D Mesh Generator and Graphical Display of Geometry for Radiation Transport Codes, Display of Results |
| nea-0866 | BTPLOT BTSPEC EXSPEC ORDTAB TABLST, Retrieval of ENDF/B Decay Spectra |
| nea-1727 | BULK-I, Radiation Shielding Tool for Proton Accelerator Facilities |
| nea-1819 | BURD, Bayesian estimation in data analysis of Probabilistic Safety Assessment |
| nea-0114 | BURST, Time-Dependent Pressure and Coolant Flow after Circuit Fracture in HTGR |
| nea-0558 | BUST, Elastic Stress in HTGR Pressurized Fuel Elements |
| nesc1080 | BWR-GALE, Radioactive Gaseous and Liquid Waste Release from BWR |
| nea-1313 | BWRDYN, Thermal Hydraulic Analysis of a BWR Plant |
| iaea1403 | C-SHIELDER, Gamma shielding calculations of radionuclides emitting photons 0.5 to 10 MeV by different concretes |
| nea-1278 | CALENDF-2010, Pointwise, Multigroup Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations |
| ccc-0594 | CALKUX, Exposure Transmission of Medical X-Ray Beams Through Barrier Materials |
| ccc-0542 | CAP-88, Dose Risk Assessment from Air Emissions of Radionuclides |
| nea-1327 | CAPCAL V1.3, 3-D Capacitance Calculator for VLSI Purposes |
| psr-0388 | CARES, Seismic Structure Safety Analysis for Nuclear Power Plants |
| nea-1735 | CARL 2.3, radiotoxicity, activity, dose and decay power calculations for spent fuel |
| psr-0262 | CASKCODES, Program CAPSIZE Scope KWIKDOSE for Shipping Cask Shielding |
| nea-1195 | CASKET, Thermal and Structural Analyses for Transport and Storage Cask |
| ests1071 | CECP(BWR) CECP(PWR), Decommissioning Costs for PWR and BWR |
| nea-0553 | CEDRAZAL, Steady-State Heat Transfer in HTR with Multifuel Region |
| psr-0532 | CEM03.03, Monte-Carlo Code system to calculate nuclear reactions in the framework of the improved cascade-exciton model |
| iaea1247 | CEM95, Cascade Exciton Model Nuclear Reactions by Monte-Carlo Method |
| ccc-0544 | CEPXS ONELD, 1-D Coupled Electron Photon MultiGroup System |
| ccc-0837 | CEPXS, Coupled Electron-Photon Cross Section |
| ests0663 | CFDLIB, Computational Fluid Dynamics Library |
| ccc-0604 | CHAINS-PC, Decay Chain Atomic Densities |
| uscd1208 | CHECKR-8.05, ENDF/B Format Check |
| nea-1561 | CHEMENGL/CHIMISTE, Chemical and Physical Properties of Elements |
| uscd1021 | CHUCK-3, Nuclear Scattering Amplitude and Collision Cross-Sections by Coupled Channel |
| 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 |
| iaea1385 | CITOPP-CITMOD-CITWI, Processing codes for CITATION Code |
| iaea0883 | CLUB, Cell Calculation PF Candu PWR Fuel Clusters |
| ccc-0726 | CNCSN 2009, One, Two- and Three-Dimensional Coupled Neutral and Charged Particle Sn Parallel Multi-Threaded Code System |
| nesc9911 | CNVUFAC GRAY, Black-Body Radiation View Factors with Self-Shadowing |
| nesc0873 | COAST-4, Design and Cost of Tokamak Fusion Reactors |
| nesc9978 | COBRA-3C/RERTR, Thermohydraulic Low Pressure Subchannel Transients Analysis |
| nesc0432 | COBRA-4I, Transient Thermohydraulics Fuel Elements Clusters, Subchannel Analysis Method |
| nea-1614 | COBRA-EN, Thermal-Hydraulic Transient Analysis of Reactor Cores |
| 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 |
| nesc1091 | COBRA-SFS, Thermal Hydraulics of Spent Fuel Storage System |
| ccc-0829 | COG11.1, Multiparticle Monte Carlo Code System for Shielding and Criticality Use |
| nea-0915 | COGEND, Decay Data Generated in ENDF-6 Format |
| psr-0607 | COGLIBMAKER2014, Data Conversion Utility |
| psr-0286 | COMBINE-PC, MultiGroup Neutron Cross-Sections in B1 or B3 Approximation from ENDF/B-5 |
| nesc0776 | COMPARE-MOD1A, 2 Phase Flow Thermodynamics, Pressure in LWR Containment |
| ests0023 | COMPBRN3, Modelling of Nuclear Power Plant Compartment Fires |
| nesc0498 | CONCEPT-5, Cost and Economics Analysis for Nuclear Fuel or Fossil Fuel Power Plant |
| ccc-0416 | CONDOS-II, Radiation Dose from Consumer Product Distribution Chain |
| nesc0818 | CONTEMPT-4/MOD5&6, LWR Containment Long-Term Pressure Distribution and Temperature Distribution in LOCA |
| nesc0433 | CONTEMPT-LT/028B & H, LWR Containment Pressure and Temperature Distribution in LOCA |
| nea-1305 | COOLOD, Steady-State Thermal Hydraulics of Research Reactors |
| iaea1226 | CORD-2, PWR Core Design and Fuel Management |
| nesc0758 | COREL DAMG2 RASE4, Ion Implantation in Solids, Range, Straggling Using Thomas-Fermi Cross-Sections |
| nea-1375 | COSIMA, BWR Core Performance Simulator |
| nea-0425 | COSTANZA-XE, 2-D Pebble-Bed or Prismatic Fuel Elements HTR Dynamic in Cylindrical Geometry |
| nea-1734 | CRISSUE-S, Neutronics/Thermal-hydraulics Coupling in LWR Technology |
| nea-1903 | CRISTAL V2.0.3, Criticality calculation package |
| iaea0873 | CRITIC, In-Core Fuel Management for CANDU PWR |
| nea-1681 | CRITICALITYACCIDENTS, A Review of Criticality Accidents, 2000 Revision, LA-13638 in PDF format |
| ccc-0233 | CRYSTAL-BALL, Neutron Spectra Calculation from Activation Experiment with Error Estimate |
| nea-1892 | CUMYIELD.MT, cumulative yields calculations of radioactive decay isotopes considering decay chain |
| nea-1535 | D2O, Computation of Thermodynamic and Transport Properties of Heavy Water |
| nea-1516 | DANCOFF-MC, Dancoff Correlation for Arbitrary Lattices by Monte-Carlo |
| nea-0694 | DANTE, Activation Analysis Neutron Spectra Unfolding by Covariance Matrix Method |
| ccc-0547 | DANTSYS3.0, 1-D, 2-D, 3-D MultiGroup Discrete Ordinate Method Transport |
| nea-1885 | DART-V.1, displacement per atom, primary knocked-on atoms produced in an atomic solid target |
| nesc9918 | DASSL, Solution of Differential Algebraic Equation |
| nesc9493 | DATING, Temperature for Spent Fuel Dry Storage |
| 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 |
| ests0848 | DDASAC, Double-Precision Differential or Algebraic Sensitivity Analysis |
| nea-1893 | DECAYHEAT.MT, decay heat calculations from radioactive isotopes |
| nesc9681 | DEM4-26, Least Square Fit for IBM PC by Deming Method |
| nea-1887 | DESAE, develop prospective nuclear energy scenarios in a regional and global scale |
| ccc-0649 | DIF3D 8.0/VARIANT8.0, 2-D 3-D Multigroup Diffusion/Transport Theory Nodal & Finite Difference Solver, Variational Method |
| ccc-0784 | DIF3D10.0, Variational Nodal Methods, Finite Difference Methods to Solve N diffusion & Transport Theory Problems |
| iaea1269 | DIFBAS, Spectra Unfolding of Ne213 P Recoil Detectors |
| nesc9639 | DIGLIB/PC, General Graphics Subroutine Package for Different Computers |
| ccc-0454 | DISPERS, Radioactive Release into Surface Water and Ground Water |
| nesc0847 | DISPL-1, 2nd Order Nonlinear Partial Differential Equation System Solution for Kinetics Diffusion Problems |
| nesc9532 | DISPOSAL-SITE, Low-Level Radioactive Waste Storage Cost Analysis |
| 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 |
| psr-0110 | DOQDP, Discrete Ordinate Quadrature Generator for Programs DOT and ANISN |
| 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-0624 | DOSE-SGTR, Iodine Release During Steam Generator Tube Rupture (SGTR) in PWR |
| 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 |
| uscd1234 | DRAGON 5.1, Reactor Cell Calculation System with Burnup |
| uscd1237 | DRAGON2PARTISN, Cross-Sections Data Generation for PARTISN4.0 |
| nesc0784 | DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plant |
| nea-0322 | DTF4-J, 1-D Neutron Transport with Anisotropic Scattering by Sn Method |
| nea-1671 | DUCT-III, Design Code for Duct-Streaming Radiations |
| ccc-0634 | DUST-BNL, Radioactive Waste Transport from Container Leaks into Ground Water |
| nea-1209 | DWBA07/DWBB07, elastic scattering with nucleon-nucleon potential and DWBA for inelastic scattering |
| nesc9872 | DWUCK-4 DWUCK-5, Scattering Cross-Sections of Spin 0 and 1/2 and 1 Particles by DWBA |
| nea-1411 | DYN3D/M2, Reactivity Transients in Light H2O Reactors with Hexagonal Geometry |
| nea-0217 | DYNAPS, Vibration Analysis of Piping System in Earthquake |
| ests1300 | E3D, 3-D Elastic Seismic Wave Propagation Code |
| nea-1875 | EACRP-D2O-LATTICES, Compilation of reactor physics measurements in HWRs lattices |
| ccc-0744 | EASYQAD 2.0.1, Visualization for Gamma and Neutron Shielding Calculations |
| nea-0850 | ECIS-12, Coupled Channel, Statistical Model, Schroedinger and Dirac Equation, Dispersion Relation |
| psr-0191 | EDISTR, Nuclear Data Base Generator for Internal Radiation Dosimetry Calculation |
| nea-0969 | EDMULT-6.4, Electron Depth Dose Distribution in Multilayer Slab Absorbers |
| psr-0531 | EEDB, The Energy Economic Data Base |
| ccc-0331 | EGS4, Electron Photon Shower Simulation by Monte-Carlo |
| nesc0983 | EGUN, Charged Particle Trajectories in Electromagnetic Focusing System |
| nea-1200 | ELEORBIT, 3-D Simulation of Electron Orbits in Magnetic Multipole Plasma Source |
| iaea1169 | EMPIRE-II 2.18, Comprehensive Nuclear Model Code, Nucleons, Ions Induced Cross-Sections |
| uscd1235 | ENDF-UTILITY-CODES, codes to check and standardize data in the Evaluated Nuclear Data File (ENDF) |
| nea-1895 | ENDSAM, a code for random sampling and validation of covariance data of resonance parameters in ENDF-6 format |
| iaea1402 | ENDVER/GUI, The ENDF File Verification Support Package |
| uscd1149 | ENSDF PROCESSING CODES, Analysis and Utility Programs |
| nea-1686 | ENTREE 1.4.0, BWR Core Simulation System for Space and Time Dependent Coupled Phenomena |
| iaea1285 | EPICSHOW-98.1, Interactive Viewing of EPIC (Electron Photon Interaction Code) Data Library |
| nesc0886 | EQ3/6, Thermodynamics Equilibrium for Aqueous Solution Mineral System |
| iaea1202 | EQUIVA, Few-Group Diffusion Parameter for PWR Reflector Region by 1-D Transport Calculation |
| nea-1683 | ERANOS 2.3N, Modular code and data system for fast reactor neutronics analyses |
| nea-1676 | ERRORJ-2.3, Multigroup covariance matrices generation from ENDF-6 format |
| iaea1282 | ESTAR PSTAR ASTAR, Stopping Power and Range of Electrons, Protons, Alpha |
| nea-0892 | ESTIMA, Neutron Width Level Spacing, Neutron Strength Function of S- Wave, P-Wave Resonances |
| ccc-0107 | ETRAN, Electron Transport and Gamma Transport with Secondary Radiation in Slab by Monte-Carlo |
| nea-1094 | EURDYN, Nonlinear Transient Analysis of Structure with Dynamic Loads |
| psr-0010 | EVAP-4, Particle Evaporation from Excited Nuclei |
| nesc9952 | EVENT, Explosive Transients in Flow Networks |
| nea-0228 | EXCURS-3, Reactor Kinetics and Heat Transfer in Cylindrical Channel During Accident |
| iaea1273 | EXCURS-3-RR, Kinetics of Research Reactor Reactivity Transient Analysis |
| iaea1211 | EXIFON2.0, Neutron, Alpha, Proton, Gamma Emission Spectra |
| nesc0156 | EXTERMINATOR-2, 2-D MultiGroup Neutron Diffusion in X-Y R-Z or R-Theta Geometry |
| nesc9578 | FACET, Radiation View Factor with Shadowing |
| ests0063 | FAMREC, PWR Lateral Mechanical Fuel Rod Assembly Response |
| nea-0617 | FAPMAN-IC, LWR Fuel Cost Analysis with Program ORSIM Interface |
| nesc1095 | FASTGRASS, Gaseous Fission Products Release in UO2 Fuel |
| iaea1438 | FE-SHIELDER, shielding thickness of Iron for any photon emitting radionuclide between 0.5 and 10 MeV |
| nea-0443 | FEM-2D, 2-D MultiGroup Diffusion in X-Y Geometry |
| nea-0545 | FEM-BABEL, 3-D MultiGroup Neutron Diffusion by Galerkin Method |
| nea-1080 | FEMAXI-6, Thermal and Mechanical Behaviour of LWR Fuel Rods |
| ccc-0451 | FEMWASTE FEMWATER, Finite Elements Method Waste Transport Through Porous Media |
| nesc1144 | FEMWATER BLT, Water or Waste Transport in Soil |
| psr-0102 | FERDO/FERD, Unfolding of Pulse-Height Spectrometer Spectra |
| nesc9844 | FFSM, Long-Term Nuclear Waste Repository Site Simulation by Monte-Carlo |
| nea-1692 | FFT-BM, Code Accuracy Evaluations with the 1D Fast Fourier Transform (FFT) Methodology |
| nea-1934 | FIFRELIN-1.7, generation of fission fragments and simulate their de-excitation to estimate prompt fission observables |
| nea-0896 | FINELM, MultiGroup Diffusion in 3-D by Finite Elements Method |
| nea-1916 | FINPSA TRAINING2.3.1, a PSA model in consisting of event trees, fault trees, and cut sets |
| nesc1092 | FIRAC, Nuclear Power Plant Fire Accident Model |
| dlc-0125 | FIREDATA, Nuclear Power Plant Fire Database |
| nea-0897 | FISP-6, Fission Products Inventory and Energy Release in Irradiated Fuel |
| nea-1890 | FISPACT-II 5.X, Inventory Simulation Platform for Nuclear Observables and Materials Science |
| nea-0706 | FISPIN, Isotope Buildup and Isotope Decay for Actinides, Fission Products, Structure Materials |
| uscd1209 | FIZCON-8.03, ENDF/B Cross-Sections Redundancy Check |
| nesc0689 | FLANGE-ORNL, Flanged Pipe Joint Stress Analysis, Internal Pressure, Moment Loads, Temperature |
| nea-1833 | FLUKA2011.2X.4, Monte Carlo general purpose tool for calculations of particle transport and interactions with matter |
| psr-0196 | FLYSPEC, Neutron Spectra Unfolding from Ne213 and Stilbene Scintillation Detectors |
| nea-0669 | FONTA, Radiation Release in Atmosphere and Deposition in Human Organs |
| psr-0092 | FORIST, Ne-213 Scintillation Detector Neutron Spectra Unfolding |
| iaea1388 | FOTELP-2018, Photons, Electrons and Positrons Transport in 3D by Monte Carlo Techniques |
| nesc9915 | FRAMIS, Relational Data Base Management System |
| psr-0363 | FRANCO, Finite Element Method (FEM) Fuel Rod Analysis for Solid and Annular Configurations |
| nesc0658 | FRAP-T6/MOD1, Temperature and Pressure in Oxide Fuel During LWR LOCA |
| nesc0694 | FRAPCON2 and FRAPCON2/V1M4, Steady-State LWR Oxide Fuel Elements Behaviour, Fission Products Gas Release, Error Analysis |
| nea-1907 | FRENDY V2, Nuclear Data Processing System for Evaluated Nuclear Data File |
| nesc0301 | FREVAP-6, Metal Fission Products Release from HTGR Fuel Elements |
| nea-1846 | FSKY4C, Gamma Ray Skyshine Analysis Code |
| nesc9659 | FTAP, Minimal Cut Sets of Arbitrary Fault Trees |
| nesc9860 | FTRANS, Radionuclide Flow in Groundwater and Fractured Rock |
| nea-1812 | FUELPERFORMANCE-REP, Seminars on nuclear fuel performance based on basic underlining phenomena, proceedings |
| nesc0862 | FX2-TH, 2-D MultiGroup Neutron Diffusion in X-Y, R-Z and R-Theta Geometry with Thermal Feedback |
| psr-0610 | GADRAS-DRF-18.8.13, Gamma Detector Response and Analysis Software-Detector Response Function |
| nesc0310 | GAKIN-2, 1-D MultiGroup Time-Dependent Neutron Diffusion, Finite Difference Method |
| nesc9654 | GAMANAL, Radioactive Species Mixtures by Gamma Spectra Analysis |
| nea-1827 | GANAPOL-ABNTT, Analytical Benchmarks for Nuclear Engineering Applications, Case Studies in Neutron Transport Theory |
| nesc0618 | GAPCON-THERMAL-2 & GT2R2-1, Steady-State Fuel Rod Thermal Behaviour and Fission Products Gas Release |
| nesc0770 | GAPCON-THERMAL3, Fuel Rod Steady-State and Transient Thermal Behaviour, Stress Analysis |
| nea-1601 | GARDEC, Estimation of dose-rates reduction by garden decontamination |
| nesc0263 | GASKET-2, Thermal Neutron Scattering Law for Moderators, Harmonic Vibrations and Gaseous |
| ccc-0463 | GASPAR-II, Radiation Exposure to Man from Air Releases of Reactor Effluents |
| nesc0380 | GATT, 3-D Few-Group Neutron Diffusion for Power Distribution in Hexagonal Reactor Core for HTGR |
| nesc0622 | GAUSS-6, Experimental Gamma Spectra Analysis, Isotope Identification, Decay Rates |
| nea-1864 | GEF 2021/1.1, Code for Simulation of Nuclear Fission Process |
| nea-1652 | GEM, Monte-Carlo Code for Simulating a Decaying Process of an Excited Nucleus |
| nesc0576 | GEM-NESC, Fuel Cycle Cost and Economics for Thermal Reactor, Present Worth Analysis |
| ccc-0737 | GENII 2.10, Environmental Radiation Dosimetry System |
| ccc-0601 | GENII-LIN, Multipurpose Health Physics Code |
| uscd1210 | GETMAT-6.13, ENDF/B Material Retrieval |
| psr-0229 | GIP, Group Organized Cross-Sections Library for ANISN, DOT |
| psr-0125 | GNASH-FKK, Preequilibrium, Statistical Model Cross-Sections and Emission Spectra |
| iaea1271 | GNOMER, Core Power Distribution by 1-D, 2-D, 3-D MultiGroup Neutron Diffusion |
| uscd1211 | GRALIB-6.11, DISSPLA Plot Routines Emulator |
| psr-0231 | GRESS-3.0, FORTRAN Precompiler with Differentiation Enhancement |
| ccc-0774 | GRSAC, Graphite Reactor Severe Accident Code |
| nea-1917 | GRSIS, program to predict fission gas release and swelling behavior in U-Pu-Zr metallic fast reactor fuel |
| ccc-0721 | GRTUNCL3D, Code to Calculate Semi Analytic First Collision Source and Uncollided Flux (X, Y, Z) |
| nea-1899 | GRUCON-D-2017-01, Data Processing for Evaluated Working libraries (transport and shielding) |
| nea-1820 | GTSP, automatic ultrasonic inspection of Guide Tube Support Pin in nuclear power plants |
| ccc-0697 | GUI2QAD, Graphical Interface for QAD-CGPIC, Point Kernel for Shielding Calculations |
| nea-0682 | H2OTP, Temperature Dependent and Pressure Dependent Thermodynamics Properties, Transport Properties of H2O |
| nesc0797 | HAARM-S, Time-Dependent Diffusion and Deposition of Radioactive Aerosols, LMFBR Accidents |
| ccc-0665 | HABIT 1.1, Toxic and radioactive release hazards in reactor control room |
| ests1100 | HABIT, Toxic and Radioactive Release Hazards in Reactor Control Room |
| nesc0277 | HAMMER, 1-D MultiGroup Neutron Transport Infinite System Cell Calculation for Few-Group Diffusion Calculation |
| nea-1345 | HARPHRQ, Geochemical Reaction Modelling |
| nea-0547 | HASSAN, Time-Dependent Temperature Distribution and Stress and Strain in HTR Fuel Pins |
| nesc9819 | HCT, Time Dependent 1-D Gas Hydrodynamics, Chemical Kinetics, Chemical Transport |
| psr-0199 | HEATING-7.3, Multidimensional Finite-Difference Heat Conduction Analysis |
| nea-0490 | HEDO-2, Magnetic Field Calculation and Plot of Air Core Coils |
| nea-0302 | HEITLER, Compton Cross-Sections, Photoelectric Cross-Sections, Pair-Production Cross-Sections, Total Cross-Sections |
| nesc0775 | HEMP, 2-D Elastic Plastic Flow in 2-D X-Y or Cylindrical Geometry by Lagrangian Method |
| nea-1666 | HEPROW, Unfolding of pulse height spectra using Bayes theorem and maximum entropy method |
| nea-0536 | HERA-1A, Steady-State Thermohydraulics of Na Cooled Fuel Rod Bundles |
| ests0545 | HGSYSTEM, Atmospheric Dispersion for Ideal Gases and Hydrogen Fluoride (HF) |
| ccc-0644 | HOTSPOT 3.0.1, Health Physics Code System for Evaluating Accidents Involving Radioactive Materials |
| nea-1935 | HRP-LEGACY-DB, Halden Reactor Project Legacy Database |
| ests0406 | HYFRACP3D, 3-D Hydraulic Fracture Propagation by Finite Element Method |
| nea-1823 | ICRS1, Proceedings of the First Radiation Shielding Symposium, Cambridge, UK 1958 |
| ests0005 | IMPACTS-BRC2.1, General Radiological Impacts Analysis |
| iaea1378 | INDOSE V2.1.1, Internal Dosimetry Code Using Biokinetics Models |
| nea-1904 | INES-CLASS, assessment of accidents significance occurred at nuclear facilities |
| psr-0313 | INFLTB, Dosimetric Mass Energy Transfer and Absorption Coefficient |
| uscd1212 | INTER-8.00, ENDF/B Thermal Cross-Sections, Resonance Integrals, G-Factors Calculation |
| iaea0886 | INTERTRAN-I & II, Radiation Exposure from Vehicle Transport of Radioactive Material |
| uscd1213 | INTLIB-6, Graphic Device Interface Library for ENDF/B Processing Codes |
| nea-1894 | INVENTDYN.MT, calculates the dynamics of the amount of isotope and its daughter nuclides with time stamps |
| nea-1821 | IPLOT, interactive MELCOR data plotting system |
| iaea1328 | ISABEL EVA PACE-2, Evaporation Model with Intranuclear Cascade Input |
| 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. |
| iaea0940 | JADSPE, Multi-Channel Gamma Spectra Unfolding Program |
| nea-1760 | JANIS 4.0, a Java-based nuclear data display program |
| nea-1838 | JASMINE V.3, Steam explosion simulation |
| nea-1811 | JDL-IMPORTANCE, Adjoint Function: Physical Basis of Variational & Perturbation Theory in Transport & Diffusion Problems |
| nea-1843 | JDL-REACTOR-KINETICS, Nuclear Reactor Kinetics and Control |
| nea-1844 | JDL-THERMODYNAMICS, Thermodynamics: Frontiers and Foundations |
| nea-0624 | JOSHUA, Neutronics, Hydraulics, Burnup, Refuelling of LWR |
| psr-0306 | KAOS-V, Neutron Fluence to Kerma Factor Evaluation from ENDF/B-5 and JENDL-2 |
| ccc-0510 | KENO-IV(RG), KENO-IV with Random Geometry |
| psr-0541 | KENO2MCNP, Version 5L, Conversion of Input Data between KENOV.a and MCNP File Formats |
| psr-0450 | KENO3D 5.1, Visualisation Tool for KENO V.A and KENO-VI Geometry Models |
| ccc-0548 | KENO5A-PC, Monte-Carlo Criticality with Supergrouping |
| nea-0288 | KERBREK, Fuel Cycle Cost Analysis for Power Reactor |
| nea-1865 | KICHE 1.3, Kinetics of Iodine Chemistry in the Containment of LWRs under Severe Accident Conditions |
| iaea1339 | KINETIK, Time-Dependent Heat and Mass Transfer |
| ests0154 | KIVA3VRELEASE2, Transient Multicomponent 2-D and 3-D Reactive Flows with Fuel Sprays |
| nea-1001 | KORIGEN, Isotope Inventory, Radiation Heat from PWR Burnup |
| nea-0441 | KPD, Time-Dependent Fuel Cycle Cost Calculation for Various Reactor Types |
| nea-1924 | KRAKEN 1.2.X, framework of (coupled) tools for reactor core analysis |
| nesc0992 | LADTAP-2, Organ Doses to Man and Other Biota from Aquatic Environment |
| ccc-0696 | LAHET 2.8, Code System for High Energy Particle Transport Calculations |
| nea-0192 | LAZY, General Experimental Data Processing Program |
| psr-0277 | LEPRICON, PWR Vessel Dose Analysis with DORT and ANISN Program |
| nea-0124 | LGH, Gamma Streaming and Neutron Streaming for Duct |
| psr-0394 | LHS, Multivariate Sample Generator by Latin Hypercube Sampling |
| nesc1085 | LHS-ESTSC, Multivariate Sample Generator by Latin Hypercube Sampling |
| uscd1214 | LISTEF-6.13, ENDF/B Data File Summary List |
| nea-1026 | LOUHI82, Generator Spectra Unfolding Program with Linear and Nonlinear Regularization |
| psr-0233 | LSL-M2, Neutron Spectra Log Adjustment for Dosimetry Applications |
| uscd1224 | LSODI, Implicit Ordinary Differential Equations System Either Dense or Banded Matrices |
| nea-0316 | LTFR-4, Library Generated for Fast Reactor Design Program from JAERI Fast-Set MultiGroup Constant |
| ccc-0631 | LWRARC-1.0, PWR and BWR Spent Fuel Decay Heat Generator |
| nesc1006 | MAEROS, Multicomponent Aerosol Time Evolution |
| nea-1047 | MANYCASK, Radiation Dose Rate Around Many Casks |
| nea-0517 | MAPLIB, Thermodynamics Materials Property Generator for FORTRAN Program |
| ccc-0503 | MARINRAD, Health Hazard from Radioactive Material Release into Ocean |
| psr-0137 | MARLOWE 15b, Computer Simulation of Atomic Collisions in Crystalline Solids |
| nea-1307 | MARMER, Point-Kernel Shielding Calculation with Nuclide Concentrations from ORIGEN-S |
| psr-0117 | MARS-ORNL, Processing Program Collection for AMPX, CCCC, ANISN, DOT, MORSE Format Library |
| ests0212 | MASCON, Mass-Consistent Atmospheric Flux Model |
| ests0279 | MATHEW/ADPIC, Air Concentration and Ground Deposition from Point Sources |
| ests0221 | MAXWELL3, 3-D FEM Electromagnetics |
| psr-0350 | MC*2-2, Calculation of Fast Neutron Spectra and Multigroup Cross-Sections from ENDF/B Data |
| uscd1241 | MCART, solve the time dependent neutron transport equation |
| 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 |
| iaea0889 | MCRAC/RBI, In Core Fuel Management, Program of PFMP System |
| ests1678 | MCSLTT, Monte Carlo Simulation of Light Transport in Tissue |
| nea-1859 | MCUNED, MCNPX Extension for Using light Ion Evaluated Nuclear Data library |
| nea-1166 | MCVIEW, 3-D Radiation View Factor by Monte-Carlo Method |
| ccc-0156 | MECC-7, Medium-Energy Intranuclear Cascade Code System |
| nea-0583 | MEDUSA-PIJ, 1-D Thermohydraulic Analysis of Laser Driven Plasma |
| nea-1889 | MEGA, Mechanistic and Engineering Fission Gas Release Model for a Uranium Dioxide Fuel |
| nea-1930 | MELGENBRIEF, A Code To Extract Control Volume Information From MELGEN Output File of The MELCOR code |
| 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 |
| ests0331 | MESORAD1.4, Emergency Response Airborne Dose Assessment |
| nea-1534 | MESYST, Simulation of 3-D Tracer Dispersion in Atmosphere |
| nea-1922 | MEXTRA 1.1, A Code To Extract Numerical Value From MAAP Code Output Files |
| psr-0542 | MGA8, Determine Pu Isotope Abundances from Multichannel Analyzer Gamma Spectra |
| nesc9460 | MILDOS-AREA, Radiological Impact of Airborne U238 from Mining and Milling |
| uscd1097 | MINEQL, Chemical Equilibrium Composition of Aqueous Systems |
| nesc0888 | MINPACK-1, Subroutine Library for Nonlinear Equation System |
| nea-1706 | MMRW, Canadian and early British Energy Reports on Nuclear Reactor Theory (1940-1946) |
| nea-1792 | MMRW-BOOKS, Legacy books on slowing down, thermalization, particle transport theory, random processes in reactors |
| ccc-0841 | MMS3D, Method of Manufactured Solutions for 3D one-group SN Equations with escalating order of non-smoothness |
| psr-0365 | MOCUP, MCNP/ORIGEN Coupling Utility Programs |
| nea-0527 | MONK, Keff, Collision Rate, Flux Distribution in General Geometry from UKNDL by Monte-Carlo Method |
| nea-1747 | MONTE-CARLO-WS-2005, Proceedings of Monte Carlo Criticality Calculations & TRIPOLI-IV Workshops 2005 |
| psr-0455 | MONTEBURNS 2.0, An Automated, Multi-Step Monte Carlo Burnup Code System |
| nea-1905 | MORET 5.D.1, Monte Carlo simulation tool to solve transport equation for neutrons |
| nea-1633 | MOSRA-LIGHT, High Speed 3-D X-Y-Z Nodal Diffusion Code for Vector Computers |
| nea-1896 | MOSRA-SRAC, Lattice Calculation Module of the Modular Code System for Nuclear Reactor Analyses MOSRA |
| iaea1349 | MSM-SOURCE, Neutron Source Generator for MCNP from Proton Neutron Interaction |
| nea-1845 | MURE v2 - SMURE, MCNP Utility for Reactor Evolution: couples Monte-Carlo transport with fuel burnup calculations |
| nea-1673 | MVP/GMVP V.3, MC Codes for Neutron & Photon Transport Calc. based on Continuous Energy and Multigroup Methods |
| nea-1926 | N-THERMALISATION, Notes on the scattering of thermal neutrons |
| iaea1411 | NAAPRO, Neutron Activation Analysis Prognosis and Optimization code |
| psr-0085 | NAISAP, Theory and Use of Gamma-Ray Spectrum Analysis Codes for NaI(Tl) Detectors. |
| nesc9644 | NASA-VOF2D, 2-D Transient Free Surface Incompressible Fluid Dynamic |
| nesc9568 | NASA-VOF3D, 3-D Transient, Free Surface, Incompressible Fluid Dynamic |
| nea-0853 | NAUA-MOD5, Aerosols in Reactor Containment During Meltdown |
| nea-1874 | NEACRP-H2O-LATTICES, Compilation of reactor physics measurements in LWRs lattices |
| ccc-0641 | NESTLE 5.2.1, Few-Group Neutron Diffusion for Steady-State and Transient Problems by Nodal Expansion Method (NEM) |
| nea-0823 | NEUPAC, Experimental Neutron Spectra Unfolding with Sensitivities |
| nea-1025 | NJOY-UTILITIES-EIR, Utility Program EPLOTR, CPLOTR, SEPR, COMBR, DECAYR for NJOY |
| psr-0480 | NJOY99.24, Data Processing System of Evaluated Nuclear Data Files ENDF Format |
| nea-0974 | NMTC/JAERI97, High-Energy P, N, Pion Reaction Monte-Carlo Simulation |
| ccc-0684 | NRCDOSE 2.3.20, Evaluation of Routine Radioactive Effluents from Nuclear Power Plants |
| ccc-0768 | NRCDOSE72 1.2.3, Evaluation of Routine Radioactive Effluents from Nuclear Power Plants with Windows Interface |
| ests1049 | NRCPIPES, Fracture Mechanics of Cracked Pipes |
| nea-0700 | NRESP4, Organic Scintillation Detector Response to Monoenergetic Fast Neutron |
| iaea1389 | NRSC, Neutron Resonance Spectrum Calculation System |
| nea-1347 | NSLINK, Coupling of NJOY Cross-Sections Generator Code to SCALE-3 System |
| nesc0790 | NUBOW-2D/INEL, 2-D Core Restraint System Stress Analysis, with Bowing, Creep, Swelling |
| iaea1320 | NUCHART, Nuclear Properties and Decay Data Chart |
| nea-1492 | NUCLEUS-CHART, Interactive Chart of Nuclides |
| nesc0683 | NUFUEL, Conditions for Power Production, U Fuel, Pu Recycle and Reprocessing |
| psr-0616 | NucWiz, set up and run Monte Carlo calculations |
| uscd1232 | ODEPACK, Initial Value Problems of Ordinary Differential Equation System |
| nea-1591 | OMEGA, Subcritical and Critical Neutron Transport in General 3-D Geometry by Monte-Carlo |
| nea-1877 | OPBA, Operator Procedural Behavior Analyzer |
| nesc0703 | ORCENT-2, Full Load Steam Turbine Cycle Thermodynamics for LWR Power Plant |
| nesc0588 | ORCOST-2, PWR, BWR, HTGR, Fossil Fuel Power Plant Cost and Economics |
| 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-1249 | ORION-II, Concentration and Dose from Radioactive Release into Atmosphere |
| nea-1880 | ORIP-XXI, isotope transmutation simulations |
| psr-0275 | ORMONTE, Uncertainty Analysis for User-Developed System Models |
| psr-0538 | P-CARES 2.0.0, Probabilistic Computer Analysis for Rapid Evaluation of Structures |
| nesc0901 | PAD, Coupled Neutronics, Thermohydraulics in 1-D Spherical, Cylindrical, Planar Geometry |
| psr-0156 | PAPIN, Cross Section, Self-Shielding Factors for Fertile Isotopes in Unresolved Resonance Region |
| psr-0516 | PARET-ANL, Code System to Predict Consequences of Nondestructive Accidents in Research and Test Reactor Cores |
| 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 |
| nea-1680 | PASCAL, Probabilistic Fracture Mechanics Analysis of Structural Components in Aging LWR |
| ccc-0445 | PAVAN, Atmospheric Dispersion of Radioactive Releases from Nuclear Power Plants |
| ests0071 | PC-PRAISE, BWR Piping Reliability Analysis |
| ests0764 | PCDOSE, Radioactive Dose Assessment and NRC Verification |
| nesc9917 | PCHIP, Piecewise Cubic Hermite Data Interpolation |
| uscd1205 | PCNUDAT, Nuclear Properties Data Base and Retrieval 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 |
| uscd1207 | PHREEQC & PHRQCGRF, Modeling of Geochemical Reactions, Calculation of pH, REDOX Potential |
| psr-0568 | PICES, Probabilistic Investigation of Capacity and Energy Shortages |
| nea-1612 | PIN99W, Modelling of VVER and PWR Fuel Rod Thermomechanical Behaviour |
| nea-0416 | PIPE, 1-D Gamma Transport for Slab, Spherical Shields with Compton Scattering Calculation |
| nea-1879 | PLOT-S, Plotting Program with special Features for Windows Environment |
| uscd1215 | PLOTEF-6.13, ENDF/B Data Plot |
| nea-0493 | PLUDOS, Ground Level Gamma Dose from Radioactive Release at Various Heights |
| nea-1663 | PLUTON, Isotope Generation and Depletion in Highly Irradiated LWR Fuel Rods |
| nea-1789 | PMK2-VVER440-REPORTS, Final reports on the PMK-2 projects for VVER Safety Studies |
| ests0428 | POISSON SUPERFISH, Poisson Equation Solver for Radio Frequency Cavity |
| iaea0944 | POLLA/IEACTA, ENDF/B Reich-Moore to Adler-Adler Resonance Parameter Conversion |
| nea-1929 | POSY, Power system model for system costs evaluation |
| nea-1675 | PPICA, Power Plant Investment Cost Analysis |
| nea-1485 | PREP-45, Input Preparation for CITATION-2 |
| nea-1173 | PREP/SPOP, Input Preparation for Monte-Carlo Program SPOP |
| iaea1379 | PREPRO2021, Data Preparation and Management, Subsidiary Calculations (ENDF Format) |
| nea-0169 | PROCOPE, Collision Probability in Pin Clusters and Infinite Rod Lattices |
| iaea1174 | PSAPACK, Probabilistic Safety Analysis with Fault Event Trees |
| uscd1216 | PSYCHE-8.00, ENDF/B Data Consistency Check in ENDF Format |
| nesc0155 | PTH-1, Pressure and Temperature in Containment after Blowdown of H2O Coolant System |
| ccc-0618 | PTRAN, Proton Transport for 50 to 250 MeV by Monte-Carlo |
| psr-0534 | PUFF-IV 6.1.0, Code System to Generate Multigroup Covariance Matrices from ENDF/B-VI Uncertainty Files |
| iaea1228 | PULSTRI-1, Mixed Core Triga Reactor Pulse Calculation |
| nea-1679 | PVIS-4, Pressure vessel irradiation, source preparation |
| nesc1081 | PWR-GALE, Radioactive Gaseous Release and Liquid Release from PWR |
| nesc0552 | PWR-PPM, Boration-Dilution Tables Generator for PWR Operation |
| nea-1828 | Proceedings of PHYSOR'90 conference: Physics of Reactors, Operation, Design and Computation, Marseille, 23-27 April 1990 |
| nea-1933 | Proceedings of the 12th International Conference on Nuclear Criticality Safety (ICNC2023), 1-6 Oct. 2023, Sendai |
| nea-1912 | Proceedings of the 7th International Conference on Nuclear Criticality Safety (ICNC2003), 20-24 Oct. 2003, Tokai-Mura |
| 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-1600 | QUARK, 2-Group 3-D Neutronic Kinetics Coupled to Core Thermalhydraulics |
| ests0062 | RABFIN PARTS, Noble Gas, Iodine, Particulate Gaseous Effluent Dose Parameters |
| nea-0467 | RADHEAT, Transport, Heat Generator, Radiation Damage Cross-Sections in Reactor and Shield |
| ccc-0800 | RADTRAD 3.03, Model for Radionuclide Transport and Removal and Dose Estimation |
| nea-1867 | RAPID, RAdial power and burnup Prediction by following fissile Isotope Distribution in the pellet |
| nea-0632 | RAPVOID, H2O Flow and Steam Flow in Pipe System with Phase Equilibrium |
| ccc-0783 | RASCAL 4.3, Radiological Assessment Systems for Consequence AnaLysis |
| ccc-0632 | RBD, Doses from Radionuclide Inhalation, Ingestion, Wound Uptake from Bioassays |
| nea-1873 | REACTORPHYSICS-62-91, Archive of Reactor Physics Reports and Summaries of [N]EACRP (1962-1991) |
| nea-1814 | REACTORSHIELDING-NMS, Reactor Shielding for Nuclear Engineers by N. M. Schaeffer |
| 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 |
| nesc9967 | RECOG-ORNL, Pattern Recognition Data Analysis |
| nesc1065 | REFCO83, Nuclear Fuel Cycle Cost Economics Using Discounted Cash Flow Analysis |
| nea-0914 | REFIT-2009, Multilevel Resonance Parameter Least Square Fit of N Transmission, Capture, Fission & Self Indication Data |
| nea-1231 | REFREP, Near-Field Model for Spent Fuel Repository |
| nesc0369 | RELAP-4, Transient 2 Phase Flow Thermohydraulics, LWR LOCA and Reflood |
| nea-0437 | RELAP-UK, Thermohydraulic Transients and Steady-State of LWR |
| nesc0917 | RELAP5/MOD1/029, Transient 2 Phase Flow Thermohydraulics, LWR LOCA Accidents |
| psr-0482 | REMIT5.1, Radiation exposure monitoring and information transmittal system |
| ccc-0786 | RESRAD 6.5, Residual Radioactive Material Guideline Implementation |
| nea-0979 | RETRANS, Reactivity Transients in LWR |
| nesc0453 | RICE, Energy Exchange Matrix, Damage Cross-Sections, Recoil Energy Spectra from ENDF/B |
| nesc9580 | RICKI, Interactive Gamma Spectra Unfolding with Isotope Identification |
| nea-1825 | RIMACS, Reactor Inspection Main Control System |
| ccc-0623 | RISKIND, Radiological Risk Assessment for Spent Nuclear Fuel Transportation |
| ccc-0626 | RIVER-RAD, Radionuclide Transport in Surface Waters |
| nea-1835 | ROCKWELL-RSDM, Reactor Shielding Design Manual by Rockwell T. III |
| ests0608 | RSAC-6, Gamma doses, inhalation and ingestion doses, fission products inventory after fission products release |
| ccc-0761 | RSAC-7.2, Gamma doses, inhalation and ingestion doses, fission products inventory after fission products release |
| nea-0402 | SABINE-3, Neutron Penetration and Gamma Penetration in Reactor Shield for Planar, Spherical, Cylindrical Geometry |
| psr-0242 | SABRINA, Geometry Plot Program for MCNP |
| 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 |
| psr-0573 | SAEROSA, Single-Species Aerosol Coagulation and Deposition with Arbitrary Size Resolution |
| nesc0332 | SAFE-3D, Stress Analysis of 3-D Composite Structure by Finite Elements Method |
| nesc0674 | SAFTAC, Monte-Carlo Fault Tree Simulation for System Design Performance and Optimization |
| nea-0212 | SAHYB-2, Solution of Ordinary Differential Equation with User-Supplied Subroutine |
| psr-0158 | SAMMY 8.1.0, Multilevel R-Matrix Fits to Neutron and Charged-Particle Cross-Section Data Using Bayes' Equations |
| nea-0691 | SAMPO80, Ge(Li) Detector Gamma Spectra Unfolding with Isotope Identification |
| ccc-0112 | SAND-II, Neutron Flux Spectra from Multiple Foil Activation Experiment |
| ccc-0361 | SANDYL, 3-D Time-Dependent and Space-Dependent Gamma Electron Cascade Transport by Monte-Carlo |
| nesc0641 | SAP-4, Static and Dynamic Linear System Stress Analysis for Various Structures |
| psr-0608 | SAPHIRE 8.0.9, Systems Analysis Programs for Hands-On Integrated Reliability Evaluations |
| nea-1898 | SAUNA V1.1, Severe Accident UNcertainty Analysis |
| nea-1405 | SCALPLO, Plotting of Flux Output from SCALE Program |
| psr-0352 | SCAMPI, Problem Dependent Library Preprocessing in AMPX Format |
| nesc1119 | SCANS, Shipping Cask Design Safety Analysis |
| nea-0829 | SCAT-2 & SCAT-2B, Cross Sections and Angular Distributions for Spherical Nuclei by Optical Model |
| ccc-0826 | SCEPTRE 1.7, Sandia Computational Engine for Particle Transport for Radiation Effects |
| psr-0267 | SCINFUL, Scintillation Neutron Detector Response by Monte-Carlo |
| nea-1755 | SCIP V1.1, Radioactive Surface Contamination Investigation Program |
| psr-0210 | SCOPE, Shipping Cask Optimization and Parametric Evaluation |
| nea-0865 | SCRIMP, Steady-State Thermohydraulics of HTGR Subchannel |
| ccc-0620 | SEECAL-2.0, Specific Effective Energy in Human Body Due to Radiation |
| nesc1063 | SEISIM-1, Seismic Probabilistic Risk Assessment |
| nea-0654 | SELFS-3, Self-Shielding Correlation of Foil Activation Neutron Spectra Analysis by SAND-2 |
| ccc-0729 | SERA-1C1, Simulation environment for radiotherapy applications |
| 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 |
| uscd1217 | SETMDC-6.13, Preprocessor for CHECKR, FIZCON, INTER, etc. ENDF Utility source codes |
| nesc0452 | SHELL-5, Elastic Stress Analysis of 3-D Thin Shells Using Finite Elements Method |
| 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 |
| iaea1416 | SIGACE, Code for Doppler broadening of ACE-formatted files |
| ests0238 | SIMION, Electrostatic Lens Analysis and Design |
| nea-1577 | SKETCH-N 1.0, Solve Neutron Diffusion Equations of Steady-State and Kinetics Problems |
| ccc-0646 | SKYSHINE-KSU, Gamma Skyshine Doses by Integral Line-Beam Method |
| ccc-0289 | SKYSHINE2&3-SKYIII-PC, Dose Rate Outside Concrete Steel Building from 6 MeV Gamma by Monte-Carlo |
| ccc-0704 | SLIDERULE 1.0,Slide Rule for direct radiation exposure approximation in criticality accidents |
| nesc1077 | SMACS, Probabilistic Seismic Analysis Chain with Statistics |
| nea-1767 | SMAFS, Steady-state analysis Model for Advanced Fuelcycle Schemes |
| nea-1046 | SMART, Radiation Dose Rates on Cask Surface |
| psr-0345 | SNL-SAND-II, Neutron Flux Spectra from Multiple Foil Activation Analysis |
| nesc0559 | SOFIRE-2, Containment Temperature and Pressure During Na Pool Fire, 1-Cell or 2-Cell Analysis |
| nesc0832 | SOLA-DF, Time-Dependent 2-D 2 Phase Flow, Eulerian Method with Various Boundary Conditions |
| nesc0651 | SOLA-SURF, 2-D Plane, Axisymmetric, Incompressible Flow Navier Stokes Equation for Transient |
| nesc0948 | SOLA-VOF, 2-D Transient Hydrodynamic Using Fractional Volume of Fluid Method |
| nesc9944 | SOLGASMIX-PV, Chemical System Equilibrium of Gaseous and Condensed Phase Mixtures |
| uscd1100 | SOLUPLOT, Eh-pH Diagram, a02-pH Diagram Plots for Aqueous Chemical Systems |
| nesc0662 | SOLVEX, Dynamic and Steady-State Mixer-Settler and Centrifugal Contactor Behaviour |
| nea-1911 | SOPHIA, a Lagrangian-based CFD code for nuclear thermal-hydraulics and safety applications. |
| nea-0450 | SOTHIS, PWR Fuel Cycle Equilibrium Cost Evaluation |
| ccc-0661 | SOURCES-4C, Calculating Alpha, N, Fission, Delayed Neutron Sources and Spectra |
| 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-1165 | SPEEDI & EXPRESS, Radiation Dose from Plume Release in Nuclear Accident |
| nea-0374 | SPES, Fuel Cycle Optimization for LWR |
| nesc0716 | SPRAY-3, Thermodynamics and Heat Transfer of Na Sprays in LMFBR after Pipe Failure |
| psr-0266 | SPUNIT, Multisphere Neutron Spectra Unfolding |
| psr-0533 | SQUIRT 1.1, predicts leakage rate and crack area for cracked pipes in nuclear power plants |
| nea-0919 | SRIM-2008, Stopping Power and Range of Ions in Matter |
| iaea1382 | SRNA-2020, Proton Transport Using 3-D by Monte Carlo Techniques |
| nea-0684 | SSYST-3, Modular System for Transient Fuel Rod Behaviour Under Accident Condition |
| iaea1439 | STACY, Very High Temp. Reactor V/HTR Safety Analyses for the Quantification of Fission Product Release from the Fuel |
| nea-1725 | STAMPI, Application to the Coupling of Atmosphere Model (MM5) and Land-surface Model (SOLVEG) |
| uscd1218 | STANEF-8.02, ENDF/B Book-keeping Operations for ENDF Format Files |
| iaea0971 | STAPRE-H95, Evaporation and Pre-Equilibrium Model Reaction Cross-Sections Calculations |
| psr-0330 | STARCODES, Stopping Power and Ranges for Electrons, Protons, He |
| nea-0908 | STATISTICS, Program System for Statistical Analysis of Experimental Data |
| nesc9749 | STATLIB, Interactive Statistics Program Library of Tutorial System |
| psr-0113 | STAY-SL, Dosimetry Unfolding with Activation, Dosimetry, Flux Error Calculation |
| nesc0487 | STEAM-67, Thermodynamics Properties of H2O and Steam from ASME Tables (1967) |
| iaea0970 | STOPOW88, Stopping Power of Fast Ions in Matter |
| iaea1437 | SUPERMC 3.3.0, Super Monte Carlo simulation program for nuclear and radiation process |
| 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 |
| ccc-0204 | SWANLAKE, Cross-Sections Sensitivity Analysis for 1-D Discrete Ordinate Calculation |
| ccc-0767 | SWORD 7.0, SoftWare for Optimization of Radiation Detectors |
| nea-0594 | SYNTH-C, Steady-State and Time-Dependent 3-D Neutron Diffusion with Thermohydraulic Feedback |
| nesc9766 | T-HEMP3D, 3-D Time-Dependent Elastic Plastic Flow |
| nesc1113 | TACT-5, Doses of Radioactivity Release from Reactor Core into Environment |
| nea-0531 | TAFEST, 2-D Transient Heat Conduction |
| ccc-0638 | TART2022, 3D Coupled Neutron-Photon Combinatorial Geometry, Time Dependent, Monte Carlo Transport Code |
| nesc0558 | TASK, 1-D MultiGroup Diffusion or Transport Theory Reactor Kinetics with Delayed Neutron |
| nea-1925 | TCOFF, Thermodynamic Char. of Fuel Debris and Fission Products based on Scenario Analysis of Severe Accident Progression |
| ccc-0180 | TDA, Time-Dependent 1-D Neutron Transport, Gamma Transport by ANISN Method in Slab, Spherical, Cylindrical Geometry |
| ccc-0709 | TDTORT, Time-Dependent, 3-D, Discrete Ordinates, Neutron Transport Code System with Delayed Neutrons |
| nea-0774 | THALES, Thermohydraulic LOCA Analysis of BWR and PWR |
| nesc9940 | THERMIT-2, 3-D Thermo-Hydraulics of BWR and PWR |
| nesc0184 | THERMOS-BRT-1, 1-D Integral Transport for Neutron Spectra, Slab and Cylinder |
| ccc-0759 | TITAN 1.29, A Three-Dimensional Deterministic Radiation Transport Code System |
| ccc-0858 | TMAP7, Tritium Migration Analysis Program |
| nesc9669 | TOPAZ-SNLL, Transient 1-D Pipe Flow Analysis |
| ccc-0543 | TORT-DORT, 1-D 2-D 3-D Discrete Ordinate Neutron and Photon Transport with Deep Penetration |
| ests0219 | TOUGH2 & TOUGHREACT, Unsaturated Ground Water and Heat Transfer |
| nesc9710 | TOXRISK, Toxic Gas Release Accident Analysis |
| nesc0836 | TRAC-PF1, Thermohydraulics, Reactor Kinetics, 2 Phase Flow LOCA Analysis |
| nea-1593 | TRAC-PF1/EN MOD 3, Best Estimate Coupled 3-D Neutronics-Thermalhydraulics |
| psr-0317 | TRANSX-2.15, Neutron Gamma Particle Transport Tables from MATXS Format Cross-Sections |
| iaea1214 | TRIGAC, Flux and Power Distribution and Burnup for TRIGA Reactor |
| iaea1370 | TRIGLAV, Research Reactor Calculations |
| 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 |
| iaea1337 | TRISTAN-IJS, Steady-State Axial Temperature and Flow Velocity in Triga Channel |
| nea-0415 | TRITON, 3-D Multi-Region Neutron Diffusion Burnup with Criticality Search |
| iaea0884 | TRIVENI, 3-D Fuel Management for PHWR CANDU |
| psr-0522 | TRUMP, Steady-State and Transient 1-D, 2-D and 3-D Potential Flow, Temperature Distribution |
| iaea1434 | U-SHIELDER, Estimates Shielding Thickness of Depleted Uranium for Photons from 0.5 to 10 MeV |
| nea-1682 | U3-U5-PU9-CRITICALS, Critical Dimensions of Systems containing U235, Pu239, and U233 |
| nea-1665 | UMG 3.3, Analysis of data measured with spectrometers using unfolding techniques |
| ests0827 | UNSPEC, X-Ray Spectrum Unfolding |
| ccc-0781 | VARSKIN 4 V4.0.0, Dose Calculation for Skin Contamination, with Sadde Input Generator |
| 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 |
| nesc0511 | VENUS-2, Reactor Kinetics with Feedback, 2-D LMFBR Disassembly Excursions |
| nesc9826 | VERTPAK-1, Fluid Flow, Rock Deformation, Solute Transport in Porous Media |
| 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 |
| uscd1240 | VIM_NC, VIM color syntax for Nuclear Codes: NJOY, DRAGON, PARTISN, TORT, MONK, and MCNP |
| nesc1115 | VISA-2, Reactor Vessel Failure Probability Under Thermal Shock |
| psr-0618 | VISUAL EDITOR 61, MCNPX/6 Visual Editor Computer Code |
| nesc0922 | VMCON, Minimization of Nonlinear Function with Constraints |
| 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 |
| iaea1417 | W-SHIELDER, calculates shielding thickness of water for photon emitting radionuclide between 0.5 to 10 MeV |
| nea-1142 | WADOSE, Radiation Source in Vitrification Waste Storage Apparatus |
| nesc9673 | WAPPA, Waste Package Performance Assessment |
| nesc0278 | WHAM-6, Pressure and Velocity Transients in Fluid Pipes, Wave Superposition Method |
| ccc-0698 | WIMS-ANL 4.0, Deterministic Code System for Lattice Calculation |
| nea-0329 | WIMS-D/4, MultiGroup Reactor Lattice Calculation for Thermal Reactor and Fast Reactor |
| iaea0887 | WIMSCORE-ENEA, 2-Group Constant from WIMS-D/4 for Programs TDB, TRITON, CITATION |
| nea-1507 | WIMSD5, Deterministic Multigroup Reactor Lattice Calculations |
| iaea1408 | WLUP3.0, 69 and 172 Group Cross Section Libraries for WIMS |
| nesc0964 | XOQDOQ, Meteorological Evaluation of Atmospheric Nuclear Power Plant Effluents |
| ccc-0847 | XOQGAM, Methodology and Software Routines for Computation of Gamma Radiation Exposures from Finite-cloud Gaussian Plumes |
| nea-1882 | XSUN-2023, Windows interface environment for transport and sensitivity-uncertainty software TRANSX-2, PARTISN and SUSD3D |
| nea-1251 | ZYLIND, Gamma Penetration for Cylindrical Source and Shield Geometry |
| nea-1398 | ZZ 3DLWRCT, 3-D LWR Rod Ejection and Rod Withdrawal Benchmarks |
| dlc-0069 | ZZ ACTL82, Data Library of Evaluated Activation Cross-Sections |
| iaea1420 | ZZ ADS-LIB, test library for Accelerator Driven Systems |
| dlc-0224 | ZZ ALBEDO-DATA, Data for the Calculation of Albedos from Concrete, Iron, Lead and Water for Photons and Neutrons |
| nea-1745 | ZZ ALEPH-LIB-JEFF3.1, MCNP Neutron Cross Section Library based on JEFF3.1 |
| nea-1927 | ZZ AMPXJEFF3.1.1UPM, AMPX-formatted Neutron Cross Section Library and Covariances based on JEFF-3.1.1 |
| nea-1928 | ZZ AMPXJEFF3.3-UPM, AMPX-formatted Neutron Cross Section Library and Covariances based on JEFF-3.3 |
| iaea1398 | ZZ BOREHOLE-EB6.8-MG, multi group cross-section library for deterministic and Monte Carlo codes |
| 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-0210 | ZZ CANDULIB-AECL, Burnup-Dependent ORIGEN-S Cross-Section Libraries for CANDU Reactor Fuels |
| dlc-0023 | ZZ CASK/F, 40-Group Neutron and Gamma Coupled Cross-Section for PWR Shipping Casks |
| iaea1256 | ZZ CENPL, Chinese Evaluated Nuclear Parameter Library |
| dlc-0042 | ZZ CLEAR/42B, 126 Neutron-Group, 36 Gamma-Group Coupled Cross-Section in AMPX, CCCC Format, for LMFBR |
| nea-1775 | ZZ CLES, cross section library of moderator materials for low-energy neutron sources |
| dlc-0271 | ZZ COG-SUP-LIB, COG Supplemental Libraries for ENDL2011 and MCNP6.1-ENDF/B-VII. 1 |
| nea-1730 | ZZ COV-15GROUP-2006, 15-group cross section covariance matrix library |
| dlc-0091 | ZZ COVFILS, 30-Group Covariance Library from ENDF/B-5 for Sensitivity Studies |
| dlc-0137 | ZZ COVFILS-2, 74-Group Neutron Cross-Section, Scattering Matrices, Covariances for Fusion Reactors |
| dlc-0028 | ZZ CTR, 73-Group Neutron and Gamma Coupled Cross-Section for CTR Transport Calculation |
| 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 |
| dlc-0030 | ZZ DECAYREM/C, Decay Spectra Library for EXREM Calculation |
| nea-1644 | ZZ DECDC, Nuclear Decay Data Files for Dose Calculation |
| dlc-0079 | ZZ DOSDAT-2, Gamma and Electron Dose Conversion Factor Data Library for Body Organs |
| dlc-0144 | ZZ DOSEDAT-DOE, Dose-Rate Conversion Factors for External Photon, Electron Exposure |
| dlc-0080 | ZZ DRALIST, Radioactive Decay Data for Dosimetry and Hazard Assessment |
| iaea1401 | ZZ DROSG-2000, Legendre Coefficient Library for 59 monoenergetic neutron source reactions |
| nea-1609 | ZZ EAF 99, Cross Section Library for Neutron Induced Activation Materials |
| nea-1606 | ZZ ECN-BUBEBO, ECN-Petten Burnup Benchmark Book, Inventories, Afterheat |
| dlc-0106 | ZZ ECPL86, Data Library of Evaluated Charged Particle Cross-Section, Nuclides Up to Oxygen |
| dlc-0208 | ZZ ELAST2, Database of Cross Sections for the Elastic Scattering of Electrons and Positrons by Atoms |
| dlc-0100 | ZZ ELECSPEC, Electron Spectra Data Library from Fission Product Decay |
| uscd0803 | ZZ ENDF/B-IV, Evaluated Nuclear Data File Version 4 |
| uscd1233 | ZZ ENDF/B-V, Evaluated Nuclear Data File Version 5 |
| dlc-0103 | ZZ ENDL86, Evaluated Charged Particle, Neutron, Photon Cross-Section Library |
| dlc-0179 | ZZ ENDLIB, Coupled Electron and Photon Transport Library in ENDL Format |
| iaea1435 | ZZ EPICS2023, Electron Photon Interaction Cross Sections |
| nea-0794 | ZZ EURLIB, Coupled Neutron Gamma Multigroup Cross-Section Library from ENDF/B for Shielding Calculations |
| iaea1364 | ZZ FENDL-2, Evaluated Nuclear Data Library for Fusion Neutronics Applications |
| dlc-0167 | ZZ FGR-DOSE, Dose Coefficient for Intake and Exposure to Radionuclides |
| nea-1822 | ZZ FLUKA05-PRE-LIB, FLUKA05 Multi-group, multi-purpose nuclear data library, neutrons, photons, charged particles |
| nea-1424 | ZZ FSXJ32&FSXLIBJ33, MCNP nuclear data library based on JENDL-3.2 and JENDL-3.3 |
| nea-1782 | ZZ FSXLIB-JD99, MCNP nuclear data library based on JENDL Dosimetry File 99 |
| nea-0878 | ZZ GAMDAT-78, Gamma Decay Data of Radioisotopes |
| dlc-0013 | ZZ GARLIB, Multigroup Resonance Cross-Section Group Constant Library for Tungsten and Depleted Pu |
| nea-1544 | ZZ GEFF-2-MATXS, Coupled Neutron-Gamma Fusion Neutronics Library in MATXS Format |
| nea-1344 | ZZ GROUPSTRUCTURES, VITAMIN-J, XMAS, ECCO-33, ECCO2000 Standard Group Structures |
| nea-1210 | ZZ HATCHES-20, Database for radiochemical modelling |
| 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-0099 | ZZ HUGO, Photon Interaction Data Library in ENDF-5 Format |
| dlc-0146 | ZZ HUGO-VI, Photon Interaction Data in ENDF-6 Format |
| iaea1419 | ZZ IBANDL, Ion Beam Analysis Nuclear Data Library in R33 format |
| nea-1656 | ZZ IEAF-2001, Intermediate Energy Activation File |
| iaea1418 | ZZ INDL/TSL, Thermal Neutron Scattering Data for H2O, D2O and ZrHx in ENDF-6 Format and as MCNP(X) Data Sets |
| iaea1215 | ZZ IRAN-LIB, Multigroup Neutron Gamma Cross-Section Library for 33 Elements in ANISN Format |
| iaea0867 | ZZ IRDF, Cross-Section Library and Spectra for Dosimetry Calculation in ENDF-5, ENDF-6 and ACE Formats |
| nea-1853 | ZZ JENDL-1, Japanese Evaluated Nuclear Data Library |
| nea-1624 | ZZ JENDL/D-99, JENDL Dosimetry Cross-Sections Data Library and Graphical Representations |
| nea-0796 | ZZ JFS-V2., Cross-Sections Library 25-Groups ABBN and 70-Group JFS for Fast Reactor Calculation |
| nea-1815 | ZZ KAFAX-E70, 150 and 12 Groups Cross Section Library in MATXS Format based on ENDF/B-VII.0 for Fast Reactors |
| nea-1650 | ZZ KAFAX-F22, 80 and 24 Groups Cross-Section Library in MATXS Format Based on JEF-2.2 for Fast Reactors |
| nea-1816 | ZZ KAFAX-F31, 150 and 12 Groups Cross Section Library in MATXS Format based on JEFF-3.1 for Fast Reactors |
| nea-1817 | ZZ KAFAX-J33, 150 and 12 Groups Cross Section Library in MATXS Format based on JENDL-3.3 for Fast Reactors |
| nea-1649 | ZZ KASHIL-E6, 175 N, 42 Gamma Groups Cross Sections in MATXS Format Based on ENDF/B-VI.5 for Shielding Applications |
| nea-1818 | ZZ KASHIL-E70, 199 N, 42 Photon Groups Cross Sections in MATXS Format Based on ENDF/B-VII.0 for Shielding Applications |
| dlc-0142 | ZZ KERMAL, Neutron and Gamma Kerma Library from ENDL and EGDL |
| dlc-0021 | ZZ KXRAY, X-Ray Attenuation Cross-Section Library from 0.1 KeV to 1 MeV |
| dlc-0168 | ZZ LA100, ENDF Format Data Library for Neutron and Protons Up to 100 MeV |
| dlc-0040 | ZZ LIB-IV, 50-Group Cross-Section Library in CCCC-III Format from ENDF/B-IV for Fast Reactors |
| 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-0177 | ZZ MATXS11, 80-Group Neutron, 24-Group Gamma Cross-Section in MATXS Format from ENDF/B-VI |
| nea-1206 | ZZ MATXS70-JEFF87, 69+1 Group MATXS Library in WIMS BOXER Structure |
| nea-1707 | ZZ MATXSLIBJ33,JENDL-3.3 based,175 N-42 photon groups (VITAMIN-J) MATXS lib. for discrete ordinates multi-group |
| nea-1668 | ZZ MCB-EAF99, MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K. |
| nea-1669 | ZZ MCB-ENDF/B6.8, MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K. |
| nea-1667 | ZZ MCB-JEF2.2, MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K. |
| nea-1670 | ZZ MCB-JENDL-3.2, MCB Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1800 K. |
| nea-1655 | ZZ MCB63NEA.BOLIB, MCNP Cross Section Library Based on ENDF/B-VI Release 3 |
| nea-1616 | ZZ MCJEF22NEA.BOLIB, MCNP Cross Section Library Based on JEF-2.2 |
| nea-1768 | ZZ MCJEFF3.1NEA, MCNP Neutron Cross Section Library based on JEFF3.1 |
| nea-1651 | ZZ MCLIB-E6, Continuous Energy Cross Section Library from ENDF/B-VI.5 for MCNP-4A, -4B, 300K, 600K, 900K |
| iaea1376 | ZZ MENDL-2P, Proton Medium Energy Nuclear Data Library |
| iaea1217 | ZZ N-SPECT/DET-RESP, Neutron Spectra and Detector Responses for Radiation Protection |
| iaea1279 | ZZ NMF-90, Database for Neutron Spectra Unfolding |
| dlc-0172 | ZZ NUCDECAY, Nuclear Decay Data for Radiation Dosimetry Calculation for ICRP and MIRD |
| dlc-0202 | ZZ NUCDECAYCALC, Nuclear Decay Data for Radiation Dosimetry Calculation for ICRP |
| nea-1642 | ZZ ORIGEN2.2-UPJ, A complete package of ORIGEN2 libraries based on JENDL-3.2 and JENDL-3.3 |
| dlc-0038 | ZZ ORYX-E, Group Constant Library from ENDF/B Fission Product Data for ORIGEN Calculation |
| iaea1423 | ZZ PADF-2007, Proton Activation Data File in ENDF-6 format |
| dlc-0236 | ZZ PHOBIA, Photon Buildup Factors to Account for Angular Incidence on Shield Walls |
| dlc-0136 | ZZ PHOTX, Photon Interaction Cross-Section Library for 100 Elements |
| nea-1868 | ZZ PIXE2010, Proton/Alpha Ionization (K,L,M shell) Tabulated Cross-Section Library |
| iaea1235 | ZZ PNESD, Diffusion Elastic Scattering Cross-Section of 3 MeV to 1000 MeV Proton on Natural Isotopes |
| iaea1409 | ZZ POINT-2004, Linearly Interpolable ENDF/B-VI.8 Data for 13 Temperatures |
| iaea1421 | ZZ POINT-2007, linearly interpolable ENDF/B-VII.0 data for 14 temperatures |
| iaea1430 | ZZ POINT-2009, a Temperature Dependent ENDF/B-VII.0 Cross Section Library |
| iaea1441 | ZZ POINT-2021, ENDF/B-VIII.0 Temperature Dependent Cross Section Library |
| dlc-0212 | ZZ POINT2000, Linearly Interpolable ENDF/B-VI.7 Data for 8 Temperatures |
| dlc-0247 | ZZ POINT2011, Linearly Interpolable ENDF/B-VII.1 Beta2 Cross-Section Library for 13 Temperatures |
| dlc-0192 | ZZ POINT97, Temperature-Dependent ENDF/B-6 Cross-Sections at 8 Temperature Between 0K and 2100K |
| dlc-0196 | ZZ PR-EDB, Power Reactor Embrittlement Database |
| iaea1277 | ZZ PRONDOS, Evaluations of Selected Neutron Activation Reactions for Dosimetry |
| dlc-0126 | ZZ PVE, 38-Group P8 Photon Cross-Section Library for Gamma Radiation Transport |
| nea-1607 | ZZ PWR-AXBUPRO-GKN, Measured Axial Burnup Profiles, NPP Neckarewstheim |
| uscd1219 | ZZ PWR-AXBUPRO-SNL, Computed Axial Burnup Profile Database for PWR |
| dlc-0134 | ZZ RADDECAY, Decay Data Library for Radiological Assessment |
| dlc-0055 | ZZ RECOIL/B, Heavy Charged Particle Recoil Spectra Library for Radiation Damage Calculation |
| nea-1545 | ZZ RFL-2-DTF, Group Constant Library of Reaction Cross-Section, Gas Production, KERMA, DPA |
| iaea1365 | ZZ RIPL & ZZ RIPL-2, Parameter Library for Nuclear Model Calculations |
| iaea1407 | ZZ RRDF-98, Cross-sections and covariance matrices for 22 neutron induced dosimetry reactions |
| dlc-0076 | ZZ SAILOR, 47 Neutron-20 Gamma-Group Coupled Cross-Section Library from VITAMIN-C by AMPX |
| nea-1185 | ZZ SCALE-LIB, Neutron-Group Constants Library from JEF-1 Using NPTXS, XLACS, XLACS-2 Programs |
| uscd1236 | ZZ SCALE5.1/COVA-44G ZZ SCALE6.0/COVA-44G, 44-group X-section covariance matrix lib. Extracted from SCALE5.1 and 6.0 |
| dlc-0045 | ZZ SENPRO/45C, Multigroup Sensitivity Library for Fast Reactors, Thermal Reactors |
| nea-1854 | ZZ SERPENT117-ACELIB, Continuous-energy X-sec lib., radioactive decay, fission yield data for SERPENT in ACE |
| dlc-0135 | ZZ SHAMSI, Coupled 43-Neutron 14-Gamma P3 Cross-Section Library for Fusion Blanket or Shield Calculations |
| dlc-0139 | ZZ SIGMA-A, Photon Interaction and Absorption Cross-Section Library |
| dlc-0093 | ZZ SKYPORT, Importance Function for Neutron and Gamma for Skyshine Dose from Accelerator |
| dlc-0178 | ZZ SNLRML, Dosimetry Cross-Section Recommendations |
| dlc-0015 | ZZ STORM-ISRAEL, Gamma Interaction Cross-Section Library in ENDF/B Format for Transport |
| iaea0865 | ZZ TEMPEST/MUFT, Thermal Neutron and Fast Neutron Multigroup Cross-Section Library for Program LEOPARD |
| nea-1837 | ZZ TENDL-2008-ACE, TENDL-2008 based library for neutrons, protons, deuterons, tritons, helions, alpha and gammas |
| iaea1399 | ZZ TH-N-CAPTURE-RI&G, Thermal Neutron Capture Cross Sections Resonance Integrals and G-Factors |
| nea-1674 | ZZ TH232-UNIBO, Th-232 cross section data for MCNP |
| dlc-0140 | ZZ THERMGAM, Thermal Neutron Capture Gamma Spectroscopical Data Library |
| dlc-0088 | ZZ TPASGAM-85, Gamma Spectra Data Library for Activation Analysis |
| nea-1883 | ZZ TSL-ACE/2013, Thermal Scattering Libraries processed to ACE format |
| nea-0899 | ZZ UKCNDL-82, Chemical Nuclear Data Library of Fission and Decay Reactions in ENDF Format |
| nea-0642 | ZZ UKCTR-1, Cross-Section Library for Neutron Flux and Neutron Reaction Rates in CTR Calculation |
| nea-0680 | ZZ UKCTRIIIA, Neutron Cross-Section Data Library for Fusion Reactor Materials Activation |
| nea-1390 | ZZ UKFY2, Fission Yields of Th, U, Np, Pu, Am, Cm, Cf Isotopes |
| dlc-0164 | ZZ UNGER, Effective Dose Equivalent Data for Selected Isotopes |
| dlc-0211 | ZZ UTXS6, MCNP Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1365 K. |
| dlc-0256 | ZZ VIP-MAN, Computational Phantom |
| nea-1264 | ZZ VITAMIN J/COVA, Covariance Matrix Data Library for Uncertainty Analysis |
| dlc-0184 | ZZ VITAMIN-B6, Fine-Group Cross-Section Library from ENDF/B-VI.3 for Radiation Transport |
| dlc-0041 | ZZ VITAMIN-C, 171 Neutron-Group, 36 Gamma-Group Coupled Cross-Section for Fusion, LMFBR Calculations |
| dlc-0113 | ZZ VITAMIN-E, 174-Group Neutron, 38-Group Gamma Cross-Section in AMPX Format |
| nea-1168 | ZZ VITAMIN-J/KERMA, Gas Production Cross-Sections, Neutron and Gamma Kerma in FOURACES 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-1702 | ZZ VITENEA-E, AMPX 174-N,38-gamma multigroup X-sec.library for multidimensional radiation transport and dose evaluation |
| nea-1703 | ZZ VITENEA-J, AMPX 175-N,42-gamma multigroup X-sect. library for nuclear fusion 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 |
| nea-1518 | ZZ WIMKAL-88, 69-Group KAERI WIMS Library for Thermal Reactors |
| iaea1397 | ZZ WIMS-D/4LIB, 61, 64, 69, 76 and 79 energy groups WIMS-D/4 libraries |
| nea-1207 | ZZ WIMS-LIB/JEF87, 69+1 Group WIMS-D Library from JEF-1 |
| dlc-0026 | ZZ WM-NRSM, Neutron and Gamma Group Cross-Section Library for Nuclear Rocket Shielding Calculations |
| nea-1610 | ZZ WPNCS BENCHM REP, Published Articles and Reports on Criticality Safety |
| dlc-0174 | ZZ XCOM, Photon Cross-Section Library for Personal Computer |
| iaea1257 | ZZ XG, Radionuclide Decay Parameters for Gamma and X-Ray Detector Calibration |
| nea-1787 | ZZ-CRYO-S(A,B)-ACE1, Scattering law and continuous energy cross section library of materials at cryogenic temperatures |
