nea-1561 |
CHEMENGL/CHIMISTE, Chemical and Physical Properties of Elements |
nea-1676 |
ERRORJ-2.3, Multigroup covariance matrices generation from ENDF-6 format |
dlc-0125 |
FIREDATA, Nuclear Power Plant Fire Database |
nea-1890 |
FISPACT-II 5.X, Inventory Simulation Platform for Nuclear Observables and Materials Science |
nea-1760 |
JANIS 4.0, a Java-based nuclear data display program |
iaea1320 |
NUCHART, Nuclear Properties and Decay Data Chart |
psr-0534 |
PUFF-IV 6.1.0, Code System to Generate Multigroup Covariance Matrices from ENDF/B-VI Uncertainty Files |
nea-1856 |
VESTA 2.1&AURORA1.0, Monte Carlo depletion interface code and AURORA 1.0.0, Depletion analysis tool |
iaea1408 |
WLUP3.0, 69 and 172 Group Cross Section Libraries for WIMS |
dlc-0069 |
ZZ ACTL82, Data Library of Evaluated Activation Cross-Sections |
iaea1420 |
ZZ ADS-LIB, test library for Accelerator Driven Systems |
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-0023 |
ZZ CASK/F, 40-Group Neutron and Gamma Coupled Cross-Section for PWR Shipping Casks |
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 |
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 |
dlc-0106 |
ZZ ECPL86, Data Library of Evaluated Charged Particle Cross-Section, Nuclides Up to Oxygen |
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 |
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-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-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-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-0021 |
ZZ KXRAY, X-Ray Attenuation Cross-Section Library from 0.1 KeV to 1 MeV |
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 |
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 |
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 |
iaea1441 |
ZZ POINT-2021, ENDF/B-VIII.0 Temperature Dependent Cross Section Library |
dlc-0247 |
ZZ POINT2011, Linearly Interpolable ENDF/B-VII.1 Beta2 Cross-Section Library for 13 Temperatures |
iaea1277 |
ZZ PRONDOS, Evaluations of Selected Neutron Activation Reactions for Dosimetry |
dlc-0134 |
ZZ RADDECAY, Decay Data Library for Radiological Assessment |
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-0178 |
ZZ SNLRML, Dosimetry Cross-Section Recommendations |
nea-1837 |
ZZ TENDL-2008-ACE, TENDL-2008 based library for neutrons, protons, deuterons, tritons, helions, alpha and gammas |
nea-1674 |
ZZ TH232-UNIBO, Th-232 cross section data for MCNP |
nea-1883 |
ZZ TSL-ACE/2013, Thermal Scattering Libraries processed to ACE format |
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 |
dlc-0174 |
ZZ XCOM, Photon Cross-Section Library for Personal Computer |
nea-1787 |
ZZ-CRYO-S(A,B)-ACE1, Scattering law and continuous energy cross section library of materials at cryogenic temperatures |