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Catalog of Programs in Category Z

Z. Data.


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
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