| nea-1561 | CHEMENGL/CHIMISTE, Chemical and Physical Properties of Elements |
| nea-1676 | ERRORJ-2.3, Multigroup covariance matrices generation from ENDF-6 format |
| nea-1934 | FIFRELIN-1.7, generation of fission fragments and simulate their de-excitation to estimate prompt fission observables |
| dlc-0125 | FIREDATA, Nuclear Power Plant Fire Database |
| nea-1890 | FISPACT-II 5.X, Inventory Simulation Platform for Nuclear Observables and Materials Science |
| nea-1935 | HRP-LEGACY-DB, Halden Reactor Project Legacy Database |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
