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Catalog of Programs in Category G

G. Radiological Safety, Hazard and Accident Analysis

nea-1072 ACFA, Isotope Activation of Coolant and Structure Materials
iaea1274 AIREKMOD-RR, Reactivity Transients in Nuclear Research Reactors
nea-1130 AIRGAMMA, External Gamma-Ray Exposure from Radioactive Cloud
uscd0795 AMRAW, Risk Assessment Method for Radioactive Waste Management
ests1169 ARCON96, Radioactive Plume Concentration in Reactor Control Rooms
nea-1581 ART MOD2, Fission Product Migration in Primary System and Containment
ccc-0417 AT123D, 1-D, 2-D, 3-D Transient Waste Transport Simulation in Groundwater
ccc-0179 ATR, Radiation Transport Models in Atmosphere at Various Altitudes
nea-1819 BURD, Bayesian estimation in data analysis of Probabilistic Safety Assessment
nea-0114 BURST, Time-Dependent Pressure and Coolant Flow after Circuit Fracture in HTGR
nesc1080 BWR-GALE, Radioactive Gaseous and Liquid Waste Release from BWR
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
ests0023 COMPBRN3, Modelling of Nuclear Power Plant Compartment Fires
ccc-0416 CONDOS-II, Radiation Dose from Consumer Product Distribution Chain
nesc0818 CONTEMPT-4/MOD5&6, LWR Containment Long-Term Pressure Distribution and Temperature Distribution in LOCA
nesc0433 CONTEMPT-LT/028B & H, LWR Containment Pressure and Temperature Distribution in LOCA
nea-1734 CRISSUE-S, Neutronics/Thermal-hydraulics Coupling in LWR Technology
nea-1535 D2O, Computation of Thermodynamic and Transport Properties of Heavy Water
ccc-0454 DISPERS, Radioactive Release into Surface Water and Ground Water
ccc-0624 DOSE-SGTR, Iodine Release During Steam Generator Tube Rupture (SGTR) in PWR
nesc0784 DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plant
ccc-0634 DUST-BNL, Radioactive Waste Transport from Container Leaks into Ground Water
psr-0191 EDISTR, Nuclear Data Base Generator for Internal Radiation Dosimetry Calculation
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 TRAINING -R-, a PSA model in consisting of event trees, fault trees, and cut sets
nesc1092 FIRAC, Nuclear Power Plant Fire Accident Model
nea-0669 FONTA, Radiation Release in Atmosphere and Deposition in Human Organs
nesc0658 FRAP-T6/MOD1, Temperature and Pressure in Oxide Fuel During LWR LOCA
nesc0694 FRAPCON2 & V1M4, Steady-State LWR Oxide Fuel Elements Behaviour, Fission Products Gas Release, Error Analysis
nesc9659 FTAP, Minimal Cut Sets of Arbitrary Fault Trees
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-0721 GRTUNCL3D, Code to Calculate Semi Analytic First Collision Source and Uncollided Flux (X, Y, Z)
nesc0797 HAARM-S, Time-Dependent Diffusion and Deposition of Radioactive Aerosols, LMFBR Accidents
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
ests0005 IMPACTS-BRC2.1, General Radiological Impacts Analysis
iaea1378 INDOSE V2.1.1, Internal Dosimetry Code Using Biokinetics Models
nea-1904 INES-CLASS, assessment of accidents significance occurred at nuclear facilities
psr-0313 INFLTB, Dosimetric Mass Energy Transfer and Absorption Coefficient
iaea0886 INTERTRAN-I & II, Radiation Exposure from Vehicle Transport of Radioactive Material
nea-1838 JASMINE V.3, Steam explosion simulation
psr-0306 KAOS-V, Neutron Fluence to Kerma Factor Evaluation from ENDF/B-5 and JENDL-2
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
psr-0233 LSL-M2, Neutron Spectra Log Adjustment for Dosimetry Applications
nea-1047 MANYCASK, Radiation Dose Rate Around Many Casks
ccc-0503 MARINRAD, Health Hazard from Radioactive Material Release into Ocean
nea-1889 MEGA, Mechanistic and Engineering Fission Gas Release Model for a Uranium Dioxide Fuel
ests0331 MESORAD1.4, Emergency Response Airborne Dose Assessment
nea-1534 MESYST, Simulation of 3-D Tracer Dispersion in Atmosphere
nesc9460 MILDOS-AREA, Radiological Impact of Airborne U238 from Mining and Milling
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
psr-0516 PARET-ANL, Code System to Predict Consequences of Nondestructive Accidents in Research and Test Reactor Cores
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
ests0764 PCDOSE, Radioactive Dose Assessment and NRC Verification
nea-1612 PIN99W, Modelling of VVER and PWR Fuel Rod Thermomechanical Behaviour
nea-0493 PLUDOS, Ground Level Gamma Dose from Radioactive Release at Various Heights
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
nea-0437 RELAP-UK, Thermohydraulic Transients and Steady-State of LWR
nesc0917 RELAP5/MOD1/029, Transient 2 Phase Flow Thermohydraulics, LWR LOCA Accidents
ccc-0786 RESRAD 6.5, Residual Radioactive Material Guideline Implementation
nea-1825 RIMACS, Reactor Inspection Main Control System
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
nesc0674 SAFTAC, Monte-Carlo Fault Tree Simulation for System Design Performance and Optimization
nea-1898 SAUNA V1.1, Severe Accident UNcertainty Analysis
nea-1755 SCIP V1.1, Radioactive Surface Contamination Investigation Program
nea-0865 SCRIMP, Steady-State Thermohydraulics of HTGR Subchannel
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
ccc-0704 SLIDERULE 1.0,Slide Rule for direct radiation exposure approximation in criticality accidents
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
nesc0716 SPRAY-3, Thermodynamics and Heat Transfer of Na Sprays in LMFBR after Pipe Failure
psr-0533 SQUIRT 1.1, predicts leakage rate and crack area for cracked pipes in nuclear power plants
nea-0684 SSYST-3, Modular System for Transient Fuel Rod Behaviour Under Accident Condition
nea-0594 SYNTH-C, Steady-State and Time-Dependent 3-D Neutron Diffusion with Thermohydraulic Feedback
nesc1113 TACT-5, Doses of Radioactivity Release from Reactor Core into Environment
nea-0774 THALES, Thermohydraulic LOCA Analysis of BWR and PWR
nesc9710 TOXRISK, Toxic Gas Release Accident Analysis
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
iaea1337 TRISTAN-IJS, Steady-State Axial Temperature and Flow Velocity in Triga Channel
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
nesc0278 WHAM-6, Pressure and Velocity Transients in Fluid Pipes, Wave Superposition Method
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