Computer Programs

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nea-1839 | ACAB-2008, ACtivation ABacus Code |

nea-1638 | ANITA-2000, Isotope Inventories from Neutron Irradiation, for Fusion Applications |

nea-1343 | ANITA-4, Isotope Inventories from Neutron Irradiation, for Fusion Applications |

ccc-0519 | AUS, Neutron Transport and Gamma Transport System for Fission Reactors and Fusion Reactors |

nesc0873 | COAST-4, Design and Cost of Tokamak Fusion Reactors |

nea-1200 | ELEORBIT, 3-D Simulation of Electron Orbits in Magnetic Multipole Plasma Source |

nea-0490 | HEDO-2, Magnetic Field Calculation and Plot of Air Core Coils |

ests0167 | ICCG2, 2-D Partial Differential Equations Linear Symmetric Matrix Solver |

ests0168 | ICCG3, 3-D Partial Differential Equations Linear Symmetric Matrix Solver |

ests0169 | ILUCG2, 2-D Partial Differential Equations Asymmetric Matrix Solver |

ests0170 | ILUCG3, 3-D Partial Differential Equations Linear Asymmetric Matrix Solver |

nea-0485 | INDRA, Fusion Reactor Blanket Neutronics, Gamma Heating, H3 Breeding |

ccc-0359 | MAGIK, Photon Dose Rates from Nucleon-Nucleus % Meson-Nucleus Collisions |

nea-0931 | MAIA, Eigenvalues for MHD Equation of Tokamak Plasma Stability Problems |

nea-1140 | MEDUSA-1B, 1-D Plasma Hydrodynamic Analysis of Fusion Pellet Ion Beams |

nea-0583 | MEDUSA-PIJ, 1-D Thermohydraulic Analysis of Laser Driven Plasma |

ests0233 | MGMHD, Multigrid 3-D for the Analysis of Magnetohydrodynamic (MHD) Channels |

nea-1181 | MORSE-DD, Monte-Carlo Neutron Transport with Combinatorial Geometry Using DDL Cross-Sections Library |

nea-0951 | NUCCON, Nuclide Concentration and Activation in D-T Fusion Reactor |

psr-0106 | PLASMX, MultiGroup Neutral Particle Transport in Tokamak CTR Plasma |

ccc-0639 | RACC-PULSE, Neutron Activation in Fusion Reactor System |

ccc-0443 | REAC*3, Isotope Activation and Transmutation in Fusion Reactors |

nesc0749 | STEEP-4, Fusion Reaction Rates for Maxwellian and Slowing-Down Plasma Ion Distribution |

iaea0943 | STRIMP, Impurity Evolution in Tokamak Fusion Reactor Discharge |

ccc-0248 | SWAN-PPL, Fusion Reactor 1-D Particle Transport Optimization |

nea-0869 | THIDA, Transmutation, Hazard Potential, Dose Rate in Fusion Reactor |

nea-0869 | THIDA-2, Transmutation, Activation, Decay Heat, Dose Rate in Fusion Reactor |

ests0551 | TMAP4, Tritium Migration Analysis Program Version 4 |

nesc0561 | TOKMINA, Toroidal Magnetic Field Minimization for Tokamak Fusion Reactor |

nesc0561 | TOKMINA-2, Total Power for Tokamak Fusion Reactor |

iaea0909 | TOPIC-RUM, Plasma Impurities in Tokamak Reactor by MHD Method |

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

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

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

dlc-0080 | ZZ DRALIST, Radioactive Decay Data for Dosimetry and Hazard Assessment |

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

iaea1364 | ZZ FENDL-2, Evaluated Nuclear Data Library for Fusion Neutronics Applications |

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

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

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

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 |

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

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

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 |

dlc-0135 | ZZ SHAMSI, Coupled 43-Neutron 14-Gamma P3 Cross-Section Library for Fusion Blanket or Shield Calculations |

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 |

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 |