Computer Programs

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ccc-0793 | AMP, Advanced Multi-Physics |

psr-0431 | ATHENA_2D, Simulation Hypothetical Recriticality Accident in a Thermal Neutron Spectrum |

nesc0191 | AX-TNT, Super Prompt Critical Excursions in Spherical Geometry, Thermohydraulics |

ccc-0459 | BOLD/VENTURE-4, Reactor Analysis System with Sensitivity and Burnup |

nea-0712 | CASSANDRE, 2-D Reactor Dynamic FEM Program with Thermohydraulic Feedback |

nesc0387 | CITATION, 3-D MultiGroup Diffusion with 1st Order Perturbation and Criticality Search |

ccc-0643 | CITATION-LDI2, 2-D MultiGroup Diffusion, Perturbation, Criticality Search, for PC |

nea-0255 | CLUS, Heat Transfer and Fuel Power in Liquid Cooled 7 Rod Fuel Elements Cluster |

nea-1614 | COBRA-EN, Thermal-Hydraulic Transient Analysis of Reactor Cores |

nea-1375 | COSIMA, BWR Core Performance Simulator |

nea-0160 | COSTANZA-AX, 1-D Neutronics and Thermodynamics of Liquid Cooled Reactor in Axial Geometry |

nea-0160 | COSTANZA-CYL, 1-D Neutronics and Thermodynamics of Liquid Cooled Reactor in Cylindrical Geometry |

nea-0333 | COSTANZA-RZ, 1-D Liquid Cooled Reactor Dynamic in R-Z Geometry |

nea-0425 | COSTANZA-XE, 2-D Pebble-Bed or Prismatic Fuel Elements HTR Dynamic in Cylindrical Geometry |

nea-0398 | COSTAX-BOIL, Transient Dynamic Analysis of BWR and PWR in Axial Geometry |

nea-1734 | CRISSUE-S, Neutronics/Thermal-hydraulics Coupling in LWR Technology |

nea-0371 | CYLFUX, Fast Reactor Reactivity Transients Simulation in LWR by 2-D 2 Group Diffusion |

nea-1506 | DPOL3D, 2 Group, 3-D Core Transients and Steady State |

nea-1411 | DYN3D/M2, Reactivity Transients in Light H2O Reactors with Hexagonal Geometry |

nea-1686 | ENTREE 1.4.0, BWR Core Simulation System for Space and Time Dependent Coupled Phenomena |

nea-0447 | EUREKA, Reactivity Transients in LWR from Control Rod, Coolant Flow, Temperature |

nea-0424 | EXCURS, Heat Transfer Transients in Cylindrical Reactor Channel LOCA |

nea-0228 | EXCURS-3, Reactor Kinetics and Heat Transfer in Cylindrical Channel During Accident |

nea-0310 | FIP-DIG, 1-D Time-Dependent Fission Products Diffusion in Slab, Cylindrical, Spherical Geometry with Gaseous Precursor |

nesc0174 | FORE-2, Thermohydraulics and Space-Independent Reactor Kinetics for Transients |

nea-0396 | FRANCESCA, 2 Phase Flow Dynamic in Boiling Test Channel and Heat Elements Conduction |

nea-0397 | FRANCESCA-BWR, 2 Phase Flow Dynamic for BWR Cooling Channel |

nesc0862 | FX2-TH, 2-D MultiGroup Neutron Diffusion in X-Y, R-Z and R-Theta Geometry with Thermal Feedback |

nesc0310 | GAKIN-2, 1-D MultiGroup Time-Dependent Neutron Diffusion, Finite Difference Method |

nea-0547 | HASSAN, Time-Dependent Temperature Distribution and Stress and Strain in HTR Fuel Pins |

ests0405 | HYFRAC3D, 3-D Hydraulic Rock Fracture Propagation by Finite Element Method |

nea-0995 | IBIS, FBR 3-D Steady-State and Kinetics with Thermohydraulic Feedback |

nea-1871 | JN-METD, N Transport with Isotropic Scattering, Bare Slabs and Homogeneous Slabs (JN-METD1), Multilayer Slabs (JN-METD2) |

nea-0492 | KAMCCO, 3-D Time-Dependent Homogeneous and Inhomogeneous Neutron Transport by Monte-Carlo Method |

nea-0112 | KINAX-3, 1-D 1 Group Reactor Kinetics with Xe and I and Fission Products Heating and Auto-Control |

nea-1293 | KINIK, Absorber Rod Calibration Kinetics |

uscd1241 | MCART, solve the time dependent neutron transport equation |

nesc0700 | MELT-3, Thermohydraulics and Neutronics, Fast Reactor Transients with Feedback |

nea-1279 | MODICO, 1-D Time-Dependent 1 Group, 2 Group Neutron Diffusion with Delayed Neutron Precursors |

nea-1635 | NIRAD, A Two-Dimensional Radiation Hydrodynamics Code |

ccc-0582 | NITRAN, Neutron Transport Code System Based on Anisotropic Scattering |

nea-1388 | NORMA, Neutron & Thermo-Hydraulic Behaviour of LWR's by Coarse-Mesh Diffusion Methods |

nea-1611 | NORMA-FP, Perform Subchannel Analysis from Converged Coarse-Mesh Nodal Solutions |

nesc0901 | PAD, Coupled Neutronics, Thermohydraulics in 1-D Spherical, Cylindrical, Planar Geometry |

iaea1216 | PRORIA, Fast Reactivity Transients in PWR with Two-Phase Flow Model |

iaea1228 | PULSTRI, Mixed Core Triga Reactor Pulse Calculation |

nea-1600 | QUARK, 2-Group 3-D Neutronic Kinetics Coupled to Core Thermalhydraulics |

nesc0474 | QX-1, 1-D MultiGroup Time-Dependent Neutron Diffusion in Planar Cylindrical and Spherical Geometry for Fast Reactors |

nea-1867 | RAPID, RAdial power and burnup Prediction by following fissile Isotope Distribution in the pellet |

nea-0101 | REP-3, Time-Dependent Xe and Sm Poisoning from Space-Dependent Flux Distribution |

ccc-0187 | SAM-CE, Time-Dependent 3-D Neutron Transport, Gamma Transport in Complex Geometry by Monte-Carlo |

ccc-0361 | SANDYL, 3-D Time-Dependent and Space-Dependent Gamma Electron Cascade Transport by Monte-Carlo |

nea-0520 | SARAZE-2, Energy Release from Reactivity Transient Fast Reactor Accident |

nea-0537 | SCOTCH, 1-D 2 Group HTGR Core Kinetics with Temperature Transients and Fluid Dynamic |

nea-1577 | SKETCH-N 1.0, Solve Neutron Diffusion Equations of Steady-State and Kinetics Problems |

nea-0468 | SPARK, Time-Dependent 1-D, 2-D, 3-D Diffusion with Heat Transfer and Feedback |

nea-0609 | SPLOSH-3, 1-D Time-Dependent Coupled Neutron Kinetics Thermohydraulics for PWR Transient |

nesc0558 | TASK, 1-D MultiGroup Diffusion or Transport Theory Reactor Kinetics with Delayed Neutron |

ccc-0180 | TDA, Time-Dependent 1-D Neutron Transport, Gamma Transport by ANISN Method in Slab, Spherical, Cylindrical Geometry |

ccc-0256 | TDT, Time-Dependent and Steady-State Reactor Kinetics with Arbitrary Delayed Neutron Group |

ccc-0709 | TDTORT: Time-Dependent, 3-D, Discrete Ordinates, Neutron Transport Code System with Delayed Neutrons |

nesc0756 | TIMEX, 1-D Time-Dependent MultiGroup Transport Theory with Delayed Neutron, Planar Cylindrical and Spherical Geometry |

nea-0387 | TIMOC-72, 3-D Time-Dependent Homogeneous or Inhomogeneous Neutron Transport by Monte-Carlo |

nea-1155 | TPTRIA, Reactivity for 2-D Triangular Geometry by Transport Perturbation Theory |

nea-1593 | TRAC-PF1/EN MOD 3, Best Estimate Coupled 3-D Neutronics-Thermalhydraulics |

nea-0807 | TRAWA, LWR Dynamic by Coupled Neutron Diffusion and Thermohydraulics Calculation |

ccc-0654 | VENTURE-PC 1.1, Reactor Analysis System with Sensitivity and Burnup |

nesc0511 | VENUS-2, Reactor Kinetics with Feedback, 2-D LMFBR Disassembly Excursions |

iaea0871 | VPI-NECM, Nuclear Engineering Program Collection for College Training |

nea-0506 | WAKE, Navier Stokes Equation with 2-D Turbulence, Stream Function, Vorticity |

nea-0564 | XBWR, 1-D Xe Transients for BWR in Axial Geometry |

nea-0283 | ZEUS-ALB.5, 3-D 1 Group Neutron Transport Kinetics in Slits, Channels, Tunnels by Monte-Carlo |