| iaea1274 | AIREKMOD-RR, Reactivity Transients in Nuclear Research Reactors |
| nea-1130 | AIRGAMMA, External Gamma-Ray Exposure from Radioactive Cloud |
| ests1169 | ARCON96, Radioactive Plume Concentration in Reactor Control Rooms |
| nea-1581 | ART MOD2, Fission Product Migration in Primary System and Containment |
| nea-1313 | BWRDYN, Thermal Hydraulic Analysis of a BWR Plant |
| ccc-0594 | CALKUX, Exposure Transmission of Medical X-Ray Beams Through Barrier Materials |
| ccc-0542 | CAP-88, Dose Risk Assessment from Air Emissions of Radionuclides |
| nea-1735 | CARL 2.3, radiotoxicity, activity, dose and decay power calculations for spent fuel |
| nesc9978 | COBRA-3C/RERTR, Thermohydraulic Low Pressure Subchannel Transients Analysis |
| nesc0432 | COBRA-4I, Transient Thermohydraulics Fuel Elements Clusters, Subchannel Analysis Method |
| nea-1535 | D2O, Computation of Thermodynamic and Transport Properties of Heavy Water |
| ccc-0624 | DOSE-SGTR, Iodine Release During Steam Generator Tube Rupture (SGTR) in PWR |
| ccc-0634 | DUST-BNL, Radioactive Waste Transport from Container Leaks into Ground Water |
| nea-0228 | EXCURS-3, Reactor Kinetics and Heat Transfer in Cylindrical Channel During Accident |
| iaea1273 | EXCURS-3-RR, Kinetics of Research Reactor Reactivity Transient Analysis |
| nesc1095 | FASTGRASS, Gaseous Fission Products Release in UO2 Fuel |
| nea-1916 | FINPSA TRAINING2.3.1, a PSA model in consisting of event trees, fault trees, and cut sets |
| nea-1601 | GARDEC, Estimation of dose-rates reduction by garden decontamination |
| ccc-0463 | GASPAR-II, Radiation Exposure to Man from Air Releases of Reactor Effluents |
| ccc-0737 | GENII 2.10, Environmental Radiation Dosimetry System |
| ccc-0601 | GENII-LIN, Multipurpose Health Physics Code |
| ccc-0774 | GRSAC, Graphite Reactor Severe Accident Code |
| ccc-0665 | HABIT 1.1, Toxic and radioactive release hazards in reactor control room |
| ests1100 | HABIT, Toxic and Radioactive Release Hazards in Reactor Control Room |
| ests0545 | HGSYSTEM, Atmospheric Dispersion for Ideal Gases and Hydrogen Fluoride (HF) |
| ccc-0644 | HOTSPOT 3.0.1, Health Physics Code System for Evaluating Accidents Involving Radioactive Materials |
| iaea1378 | INDOSE V2.1.1, Internal Dosimetry Code Using Biokinetics Models |
| nea-1904 | INES-CLASS, assessment of accidents significance occurred at nuclear facilities |
| iaea0886 | INTERTRAN-I & II, Radiation Exposure from Vehicle Transport of Radioactive Material |
| nea-1838 | JASMINE V.3, Steam explosion simulation |
| nea-1865 | KICHE 1.3, Kinetics of Iodine Chemistry in the Containment of LWRs under Severe Accident Conditions |
| psr-0277 | LEPRICON, PWR Vessel Dose Analysis with DORT and ANISN Program |
| nea-1047 | MANYCASK, Radiation Dose Rate Around Many Casks |
| nea-1889 | MEGA, Mechanistic and Engineering Fission Gas Release Model for a Uranium Dioxide Fuel |
| nea-1534 | MESYST, Simulation of 3-D Tracer Dispersion in Atmosphere |
| nea-0853 | NAUA-MOD5, Aerosols in Reactor Containment During Meltdown |
| ccc-0684 | NRCDOSE 2.3.20, Evaluation of Routine Radioactive Effluents from Nuclear Power Plants |
| ccc-0768 | NRCDOSE72 1.2.3, Evaluation of Routine Radioactive Effluents from Nuclear Power Plants with Windows Interface |
| nea-1249 | ORION-II, Concentration and Dose from Radioactive Release into Atmosphere |
| nea-1680 | PASCAL, Probabilistic Fracture Mechanics Analysis of Structural Components in Aging LWR |
| ccc-0445 | PAVAN, Atmospheric Dispersion of Radioactive Releases from Nuclear Power Plants |
| ests0071 | PC-PRAISE, BWR Piping Reliability Analysis |
| nea-1612 | PIN99W, Modelling of VVER and PWR Fuel Rod Thermomechanical Behaviour |
| iaea1174 | PSAPACK, Probabilistic Safety Analysis with Fault Event Trees |
| nesc0155 | PTH-1, Pressure and Temperature in Containment after Blowdown of H2O Coolant System |
| nesc1081 | PWR-GALE, Radioactive Gaseous Release and Liquid Release from PWR |
| ccc-0617 | QBF, Radiation Dose Distribution Around Spent Fuel Shipping Casks |
| nea-1600 | QUARK, 2-Group 3-D Neutronic Kinetics Coupled to Core Thermalhydraulics |
| ests0062 | RABFIN PARTS, Noble Gas, Iodine, Particulate Gaseous Effluent Dose Parameters |
| ccc-0800 | RADTRAD 3.03, Model for Radionuclide Transport and Removal and Dose Estimation |
| ccc-0783 | RASCAL 4.3, Radiological Assessment Systems for Consequence AnaLysis |
| ccc-0632 | RBD, Doses from Radionuclide Inhalation, Ingestion, Wound Uptake from Bioassays |
| nesc0369 | RELAP-4, Transient 2 Phase Flow Thermohydraulics, LWR LOCA and Reflood |
| nesc0917 | RELAP5/MOD1/029, Transient 2 Phase Flow Thermohydraulics, LWR LOCA Accidents |
| ccc-0786 | RESRAD 6.5, Residual Radioactive Material Guideline Implementation |
| ccc-0623 | RISKIND, Radiological Risk Assessment for Spent Nuclear Fuel Transportation |
| ests0608 | RSAC-6, Gamma doses, inhalation and ingestion doses, fission products inventory after fission products release |
| ccc-0761 | RSAC-7.2, Gamma doses, inhalation and ingestion doses, fission products inventory after fission products release |
| nea-1898 | SAUNA V1.1, Severe Accident UNcertainty Analysis |
| nea-1755 | SCIP V1.1, Radioactive Surface Contamination Investigation Program |
| ccc-0620 | SEECAL-2.0, Specific Effective Energy in Human Body Due to Radiation |
| ccc-0646 | SKYSHINE-KSU, Gamma Skyshine Doses by Integral Line-Beam Method |
| ccc-0289 | SKYSHINE2&3-SKYIII-PC, Dose Rate Outside Concrete Steel Building from 6 MeV Gamma by Monte-Carlo |
| nea-1046 | SMART, Radiation Dose Rates on Cask Surface |
| nesc0559 | SOFIRE-2, Containment Temperature and Pressure During Na Pool Fire, 1-Cell or 2-Cell Analysis |
| nea-1911 | SOPHIA, a Lagrangian-based CFD code for nuclear thermal-hydraulics and safety applications. |
| nea-1165 | SPEEDI & EXPRESS, Radiation Dose from Plume Release in Nuclear Accident |
| psr-0533 | SQUIRT 1.1, predicts leakage rate and crack area for cracked pipes in nuclear power plants |
| nea-0774 | THALES, Thermohydraulic LOCA Analysis of BWR and PWR |
| nesc0836 | TRAC-PF1, Thermohydraulics, Reactor Kinetics, 2 Phase Flow LOCA Analysis |
| nea-1593 | TRAC-PF1/EN MOD 3, Best Estimate Coupled 3-D Neutronics-Thermalhydraulics |
| ccc-0781 | VARSKIN 4 V4.0.0, Dose Calculation for Skin Contamination, with Sadde Input Generator |
| nesc1115 | VISA-2, Reactor Vessel Failure Probability Under Thermal Shock |
| iaea0871 | VPI-NECM, Nuclear Engineering Program Collection for College Training |
| ccc-0847 | XOQGAM, Methodology and Software Routines for Computation of Gamma Radiation Exposures from Finite-cloud Gaussian Plumes |
| nea-1251 | ZYLIND, Gamma Penetration for Cylindrical Source and Shield Geometry |
| iaea0867 | ZZ IRDF, Cross-Section Library and Spectra for Dosimetry Calculation in ENDF-5, ENDF-6 and ACE Formats |
