ccc-0793 |
AMP, Advanced Multi-Physics |
ccc-0459 |
BOLD/VENTURE-4, Reactor Analysis System with Sensitivity and Burnup |
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-1614 |
COBRA-EN, Thermal-Hydraulic Transient Analysis of Reactor Cores |
nea-1375 |
COSIMA, BWR Core Performance Simulator |
nea-0425 |
COSTANZA-XE, 2-D Pebble-Bed or Prismatic Fuel Elements HTR Dynamic in Cylindrical Geometry |
nea-1734 |
CRISSUE-S, Neutronics/Thermal-hydraulics Coupling in LWR Technology |
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-0228 |
EXCURS-3, Reactor Kinetics and Heat Transfer in Cylindrical Channel During Accident |
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 |
uscd1241 |
MCART, solve the time dependent neutron transport equation |
nesc0901 |
PAD, Coupled Neutronics, Thermohydraulics in 1-D Spherical, Cylindrical, Planar Geometry |
iaea1228 |
PULSTRI-1, Mixed Core Triga Reactor Pulse Calculation |
nea-1600 |
QUARK, 2-Group 3-D Neutronic Kinetics Coupled to Core Thermalhydraulics |
nea-1867 |
RAPID, RAdial power and burnup Prediction by following fissile Isotope Distribution in the pellet |
ccc-0361 |
SANDYL, 3-D Time-Dependent and Space-Dependent Gamma Electron Cascade Transport by Monte-Carlo |
nea-1577 |
SKETCH-N 1.0, Solve Neutron Diffusion Equations of Steady-State and Kinetics Problems |
nea-1911 |
SOPHIA, a Lagrangian-based CFD code for nuclear thermal-hydraulics and safety applications. |
nea-0468 |
SPARK, Time-Dependent 1-D, 2-D, 3-D Diffusion with Heat Transfer and Feedback |
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-0709 |
TDTORT, Time-Dependent, 3-D, Discrete Ordinates, Neutron Transport Code System with Delayed Neutrons |
nea-1593 |
TRAC-PF1/EN MOD 3, Best Estimate Coupled 3-D Neutronics-Thermalhydraulics |
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 |