Computer Programs
catalog | categories | new | search |

Catalog of Programs in Category 1


nea-1917 GRSIS, program to predict fission gas release and swelling behavior in U-Pu-Zr metallic fast reactor fuel
nea-1675 PPICA, Power Plant Investment Cost Analysis
nea-1485 PREP-45, Input Preparation for CITATION-2
nesc1063 SEISIM-1, Seismic Probabilistic Risk Assessment
dlc-0224 ZZ ALBEDO-DATA, Data for the Calculation of Albedos from Concrete, Iron, Lead and Water for Photons and Neutrons
dlc-0210 ZZ CANDULIB-AECL, Burnup-Dependent ORIGEN-S Cross-Section Libraries for CANDU Reactor Fuels
iaea1256 ZZ CENPL, Chinese Evaluated Nuclear Parameter 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
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
nea-0794 ZZ EURLIB, Coupled Neutron Gamma Multigroup Cross-Section Library from ENDF/B for Shielding Calculations
nea-1544 ZZ GEFF-2-MATXS, Coupled Neutron-Gamma Fusion Neutronics Library in MATXS Format
dlc-0099 ZZ HUGO, Photon Interaction Data Library in ENDF-5 Format
nea-1853 ZZ JENDL-1, Japanese Evaluated Nuclear Data Library
dlc-0142 ZZ KERMAL, Neutron and Gamma Kerma Library from ENDL and EGDL
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
dlc-0038 ZZ ORYX-E, Group Constant Library from ENDF/B Fission Product Data for ORIGEN Calculation
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
dlc-0212 ZZ POINT2000, Linearly Interpolable ENDF/B-VI.7 Data for 8 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
dlc-0126 ZZ PVE, 38-Group P8 Photon Cross-Section Library for Gamma Radiation Transport
dlc-0055 ZZ RECOIL/B, Heavy Charged Particle Recoil Spectra Library for Radiation Damage Calculation
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-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
iaea1399 ZZ TH-N-CAPTURE-RI&G, Thermal Neutron Capture Cross Sections Resonance Integrals and G-Factors
dlc-0140 ZZ THERMGAM, Thermal Neutron Capture Gamma Spectroscopical Data Library
dlc-0088 ZZ TPASGAM-85, Gamma Spectra Data Library for Activation Analysis
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.
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
iaea1257 ZZ XG, Radionuclide Decay Parameters for Gamma and X-Ray Detector Calibration