Category:
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nea-1561 | CHEMENGL/CHIMISTE, Chemical and Physical Properties of Elements |

nea-1564 | EASY-2010, European Neutron Activation System |

nea-1676 | ERRORJ, Multigroup covariance matrices generation from ENDF-6 format |

iaea1248 | INDXENDF, Preparation of Visual Catalogue of ENDF Format Data |

nea-1760 | JANIS 3.4, a Java-based nuclear data display program |

iaea1320 | NUCHART, Nuclear Properties and Decay Data Chart |

iaea1413 | PGAA-IAEA, Database for Prompt Gamma-ray Neutron Activation Analysis |

psr-0534 | PUFF-IV 6.1.0, Code System to Generate Multigroup Covariance Matrices from ENDF/B-VI Uncertainty Files |

nesc0843 | RANDOM_NUMBERS, Random Number Sequence Generated from Gas Ionisation Chamber Data |

iaea1356 | SGNUCDAT, Nuclear Data Display for IAEA Safeguard Material Analysis |

nea-1856 | VESTA 2.1.5, 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 |

nea-0789 | ZZ ABBN, 26 Group Cross-Sections and Self Shielding Factors for Fast Reactors |

nea-0790 | ZZ ACTINIDES, 84-Group Neutron Cross-Section Library for Pu242 to Es253 Isotope Production Chain |

iaea1275 | ZZ ACTIV-87, Fast Neutron Activation Cross-Section |

dlc-0069 | ZZ ACTL82, Data Library of Evaluated Activation Cross-Sections |

iaea1420 | ZZ ADS-LIB/V1.0, test library for Accelerator Driven Systems v.1.0 |

iaea1420 | ZZ ADS-LIB/V2.0, test library for Accelerator Driven Systems v.2.0 |

dlc-0049 | ZZ AIRFEWG, Gamma, Neutron Transport Calculation in Air Using FEWG1 Cross-Section |

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-0886 | ZZ AMPX-2/123, 123-Group Neutron Cross-Section Library from ENDF/B-4 by AMPX-2 |

nea-0886 | ZZ AMPX-2/219, 219-Group Neutron Cross-Section Library from ENDF/B-4 by AMPX-2 |

dlc-0027 | ZZ AMPX01/27C, Coupled Neutron-Gamma Group Constant Library by AMPX for Transport Calculation |

iaea0912 | ZZ AMZ, 70-Group 40 Isotope Multigroup Library for Fast Reactor Calculation |

dlc-0129 | ZZ ANS643, Geometric Progression Gamma-Ray Buildup Factor Coefficient Library |

dlc-0154 | ZZ ANSLV, Multigroup Cross Sections Library for ANS Reactor Design Studies |

iaea1278 | ZZ ASIYAD, Fission-Product Yield Data Library for Neutron-Induced Fission |

nea-0673 | ZZ BABEL, Multigroup Neutron Cross-Section Data Library for Fast Reactor Shield Calculation |

iaea0856 | ZZ BARC-27GRP, 27-Group Infinitely Dilute and Bondarenko Cross-Section Library from ENDF/B |

iaea1237 | ZZ BARC-75, Coupled 50 Neutron-Group 25 Gamma-Group Cross-Section Library for 42 Nuclides |

iaea1398 | ZZ BOREHOLE-EB6.8-MG, multi group cross-section library for deterministic and Monte Carlo codes |

dlc-0008 | ZZ BP-3, 104-Group Neutron Cross-Section Library for Transport Calculation |

dlc-0008 | ZZ BP-6, 104 Group Neutron and Gamma-Ray Multigroup Cross-Section Library for Transport Calculation |

iaea0949 | ZZ BROND, Evaluated Neutron Data Library in ENDF-6 Format |

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-0059 | ZZ CAD, 51 Neutron-Group, 25 Gamma-Group Albedo Data for 4 Materials from DOT Flux |

dlc-0210 | ZZ CANDULIB-AECL, Burnup-Dependent ORIGEN-S Cross-Section Libraries for CANDU Reactor Fuels |

iaea1259 | ZZ CENDL, Evaluated Nuclear Data Library for Neutron Reaction Data |

iaea1256 | ZZ CENPL, Chinese Evaluated Nuclear Parameter Library |

iaea1256 | ZZ CENPL-DLS, Discrete Level Schemes and Gamma Branching Ratios Library |

iaea1256 | ZZ CENPL-FBP, Fission Barrier Paramater Library |

iaea1256 | ZZ CENPL-GDRP, Giant Dispole Resonance Parameter Library |

iaea1256 | ZZ CENPL-MCC, Nuclear Ground State Atomic Masses Library |

iaea1256 | ZZ CENPL-NLD, Nuclear Level Density Parameter Library |

iaea1256 | ZZ CENPL-OMP, Optical Model Parameter Library |

iaea1297 | ZZ CL50G, 50-Group Multigroup Library in AMPX Format for Fast Reactor Calculation |

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-0077 | ZZ COVERV, Multigroup Cross-Section Covariance Matrices in COVERX Format |

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-0138 | ZZ COVFILS-2-I, 74-Group Neutron Cross-Section, Scattering Matrices, Covariances for Fusion Reactors |

nea-1787 | ZZ CRYO-S(A,B)-ACE1, Scattering law and continuous energy cross section library of materials at cryogenic temperatures |

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 |

nea-1538 | ZZ DECNET-GENDF, Fusion Damage Library of 175 Neutron and 42 Photon VITAMIN-J Groups |

dlc-0010 | ZZ DLC-10B AVKER, Neutron Kerma Response Function Data Library |

dlc-0011 | ZZ DLC-11 RITTS, 121-Group Coupled Cross-Section for ANISN, DOT, MORSE |

dlc-0012 | ZZ DLC-12D POPLIB, Secondary Gamma Yields and Cross-Section Library for POPOP-4 Calculation |

dlc-0013 | ZZ DLC-13B, Resonance Cross-Section Group Constant Library for Tungsten and Depleted Pu |

dlc-0014 | ZZ DLC-14 AIR, Group Constant Library of Secondary Gamma Transport in Air for ANISN Calculation |

dlc-0015 | ZZ DLC-15 STORM-ISRAEL, Gamma Interaction Cross-Section Library in ENDF/B Format for Transport |

dlc-0016 | ZZ DLC-16 COBB, 123 Neutron-Group Cross-Section Library from ENDF/B for XSDRN Calculation |

dlc-0017 | ZZ DLC-17 NOX, 119-Group Coupled Cross-Section of Nitrogen, Oxygen, Air for MORSE |

dlc-0018 | ZZ DLC-18 NAB, 100 Neutron-Group Cross-Section Library of Na and Al for ANISN, DOT, MORSE Neutron Transport |

dlc-0019 | ZZ DLC-19 DECAYGAM, Isotope Gamma Energy Library for Spectrometry Evaluation |

dlc-0021 | ZZ DLC-21, X-Ray Attenuation Cross-Section Library from 0.1 KeV to 1 MeV |

dlc-0023 | ZZ DLC-23F CASK, 40-Group Neutron and Gamma Coupled Cross-Section for PWR Shipping Casks |

dlc-0028 | ZZ DLC-28, 73-Group Neutron and Gamma Coupled Cross-Section for CTR Transport Calculation |

dlc-0002 | ZZ DLC-2D/100G, 100 Neutron-Group Cross-Section Library by SUPERTOG Calculation for ANISN, DOT |

dlc-0031 | ZZ DLC-31, 37 Neutron-Group, 21 Gamma-Group Coupled Group Constants Library from ENDF/B |

dlc-0006 | ZZ DLC-6 GAMLIB, 99-Group Cross-Section Library by SUPERTOG Calculation from ENDF/B |

dlc-0090 | ZZ DOSCOV, 24-Group Covariance Data Library from ENDF/B-V for Dosimetry Calculation |

nea-0827 | ZZ DOSCROS, Neutron Cross-Section Library for Spectra Unfolding and Integral Parameter Evaluation |

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 |

nea-1050 | ZZ EFF1LIB, Fusion Fast Neutron Data Library for MCNP |

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 |

dlc-0037 | ZZ EPR/37F, 100 Neutron-Group, 21 Gamma-Group Coupled Cross-Section for Experimental Power Reactor (EPR) Fusion System |

nea-0794 | ZZ EURLIB, Coupled Neutron Gamma Multigroup Cross-Section Library from ENDF/B for Shielding Calculations |

dlc-0085 | ZZ FCXSEC, Coupled Cross-Section Library for Shielding from VITAMIN-C in AMPX, ANISN Format |

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 |

iaea0964 | ZZ FGXRRS, 10 Neutron-Group, 7 Gamma-Group Self-Shielded Cross-Section in ANISN Format |

nea-1822 | ZZ FLUKA05-PRE-LIB, FLUKA05 Multi-group, multi-purpose nuclear data library, neutrons, photons, charged particles |

nea-1424 | ZZ FSXJ32, MCNP nuclear data library based on JENDL-3.2 |

nea-1782 | ZZ FSXLIB-JD99, MCNP nuclear data library based on JENDL Dosimetry File 99 |

nea-1424 | ZZ FSXLIBJ33, MCNP nuclear data library based on JENDL-3.3 |

nea-0878 | ZZ GAMDAT-78, Gamma Decay Data of Radioisotopes |

dlc-0071 | ZZ GAMMON, Activation Data Library for Fusion Reaction |

nea-1543 | ZZ GEFF-2-GENDF, P5 175-N and P8 42-Gamma Group Library for Fusion Blanket Applications |

nea-1544 | ZZ GEFF-2-MATXS, Coupled Neutron-Gamma Fusion Neutronics Library in MATXS Format |

nea-1102 | ZZ GEFF1, 175-Group Neutron Cross-Section in VITAMIN-J1 Format for Shielding Benchmarks |

nea-1255 | ZZ GREAC-ECN-3 REAC-ECN-4, Neutron Reaction Cross-Sections Library for Fusion Reactors |

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-0187 | ZZ HILO86R, 66 Neutron, 22 Gamma Group Cross-Section for 400 MeV Neutron, 20 MeV Gamma |

dlc-0007 | ZZ HPICE/F, Gamma Interaction Cross-Section Library in ENDF/B Format for Transport Calculation |

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-2002, 640-Group Cross-Section Library and Spectra for Dosimetry Calculation in ENDF-6 Format |

iaea0867 | ZZ IRDF-2002-ACE, Cross-Section Library and Spectra for Dosimetry Calculation in ACE Format for Monte Carlo methods |

iaea0867 | ZZ IRDF-82, 620-Group Cross-Section Library and Spectra for Dosimetry Calculation in ENDF-5 Format |

iaea0867 | ZZ IRDF-90, 640-Group Cross-Section Library and Spectra for Dosimetry Calculation in ENDF-6 Format |

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-1, Cross-Sections Library 25-Groups ABBN and 70-Group JFS for Fast Reactor Calculation |

nea-0796 | ZZ JFS-2, 25 Group (ABBN) and 70 Group JFS Cross Sections Library for Fast Reactors |

nea-0796 | ZZ JFS-3/J2, 70 Group 30 Isotopes Cross Section Library for Fast Reactors |

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 |

dlc-0160 | ZZ KAOS/LIB-V, Kerma Factors, Nuclear Response Function Library for Fission, Fusion |

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 |

iaea0870 | ZZ L26P3S34, 26-Group Constants Library of 34 Materials for Neutron Shielding Calculations |

dlc-0168 | ZZ LA100, ENDF Format Data Library for Neutron and Protons Up to 100 MeV |

dlc-0054 | ZZ LAFPX-V, Multigroup Fission Product Data Library from ENDF/B-V by Program NJOY |

dlc-0128 | ZZ LAHIMACK, Multigroup Neutron and Gamma Cross-Section and Response Function up to 800 MeV |

nesc0532 | ZZ LASL-XSECS, Fast and Thermal Multigroup Cross-Section Library in LANL Transport Format |

dlc-0040 | ZZ LIB-IV, 50-Group Cross-Section Library in CCCC-III Format from ENDF/B-IV for Fast Reactors |

dlc-0089 | ZZ LUMP, Lumped Fission Product Cross-Section Library for Fast Reactor Analysis from ENDF/B-V |

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 |

dlc-0200 | ZZ MCNPDATA, ZZ-MCB-DLC200, Standard Neutron, Photon and Electron Data Libraries for MCNP-4C and MCB1C |

iaea1376 | ZZ MENDL-2P, Proton Medium Energy Nuclear Data Library |

nea-1613 | ZZ MICROX 2 FSS LIB, Data Library for Fast Spectrum Systems Analysis |

iaea1412 | ZZ MINSKACT, Evaluated neutron reaction data for Th-232, Pa, U, Np, Pu, Am and Cm isotopes |

dlc-0033 | ZZ MONTAGE-400, Neutron Activation 100-Group Cross-Section Library of Fusion Reactor Materials |

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. |

nea-1642 | ZZ ORLIBJ32, ORIGEN2 libraries based on JENDL-3.2 |

dlc-0038 | ZZ ORYX-E/38B, 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 |

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 |

dlc-0134 | ZZ RADDECAY, Decay Data Library for Radiological Assessment |

nesc9554 | ZZ REAC-2, Nuclide Activation and Transmutation |

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 |

iaea1250 | ZZ RNPL-A, Nuclear Masses Library |

iaea1407 | ZZ RRDF-98, Cross-sections and covariance matrices for 22 neutron induced dosimetry reactions |

dlc-0057 | ZZ SAIL, Albedo Scattering Data Library for 3-D Monte-Carlo Radiation Transport in LWR Pressure Vessel |

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, 44-group cross section covariance matrix library extracted from SCALE5.1 |

uscd1236 | ZZ SCALE6.0/COVA-44G, 44-group cross section covariance matrix library extracted from SCALE6.0 |

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-0024 | ZZ SINEX, 100 Neutron-Group Neutron Reaction Cross-Section Library from ENDF/B by SUPERTOG for ANISN |

dlc-0093 | ZZ SKYPORT, Importance Function for Neutron and Gamma for Skyshine Dose from Accelerator |

dlc-0188 | ZZ SKYSDATA-KSU, Neutron and Gamma Skyshine Responses |

dlc-0178 | ZZ SNLRML, Dosimetry Cross-Section Recommendations |

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 |

nesc0543 | ZZ THERMOS, Multigroup P0 to P5 Thermal Scattering Kernels from ENDF/B Scattering Law Data |

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/B, 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-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 |

dlc-0174 | ZZ XCOM, Photon Cross-Section Library for Personal Computer |

iaea1257 | ZZ XG, Radionuclide Decay Parameters for Gamma and X-Ray Detector Calibration |