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 |