| 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 |
| 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 |
