Computer Programs
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Catalog of Programs in Category G
G. Radiological Safety, Hazard and Accident Analysis
| ccc-0442 | ACDOS3, Neutron Activation Activities and Dose Rates |
| nea-1072 | ACFA, Isotope Activation of Coolant and Structure Materials |
| nea-0621 | ACRO, Organ Doses from Acute or Chronic Radioactive Inhalation or Ingestion |
| ccc-0372 | ACT-ARA, Time-Dependent Radiation Source Terms |
| nesc0908 | AERIN, Organ and Tissue Doses from Radioactive Aerosols |
| ccc-0360 | AIRDIF, Neutron and Gamma Doses from Nuclear Explosion by 2-D Air Diffusion |
| iaea1274 | AIREKMOD-RR, Reactivity Transients in Nuclear Research Reactors |
| nea-1130 | AIRGAMMA, External Gamma-Ray Exposure from Radioactive Cloud |
| ccc-0341 | AIRSCAT, Dose Rate from Gamma Air Scattering by Single Scattering Approximation |
| ccc-0110 | AIRTRANS, Time-Dependent, Energy Dependent 3-D Neutron Transport, Gamma Transport in Air by Monte-Carlo |
| nea-0500 | ALARM, Thermohydraulics of BWR with Jet Pumps During LOCA |
| nea-0705 | ALARM-P1, PWR Thermohydraulics for ECCS During Blowdown |
| ccc-0577 | ALDOSE, Dose Rate from Alpha Disk Source in H20 |
| uscd0795 | AMRAW, Risk Assessment Method for Radioactive Waste Management |
| nesc0529 | ANVENT, Temperature Distribution and Pressure in Containment and Ice Condenser after LOCA for LWR |
| iaea1219 | APUD-3.0, Off-Site Contamination Assessment from Accidental Release |
| ests1169 | ARCON96, Radioactive Plume Concentration in Reactor Control Rooms |
| nea-1368 | ARIANNA-2, Sub-Compartment Thermo-Hydraulic Transients in LOCA |
| nea-0174 | ARLEKIN, General Point Reactor Kinetics by Lie-Series Method |
| nea-1581 | ART MOD2, Fission Product Migration in Primary System and Containment |
| nea-0539 | ASCOT-1, Thermohydraulics of Axisymmetric PWR Core with Homogeneous Flow During LOCA |
| ccc-0417 | AT123D, 1-D, 2-D, 3-D Transient Waste Transport Simulation in Groundwater |
| psr-0431 | ATHENA_2D, Simulation Hypothetical Recriticality Accident in a Thermal Neutron Spectrum |
| ccc-0179 | ATR, Radiation Transport Models in Atmosphere at Various Altitudes |
| nea-1076 | AVACOM-ETAP, Availability and Element Transient and Asymptotic Repair Process |
| nea-0861 | AWE-1 AWE-2 BRUNA, Minimal Cut Sets of Logic Trees |
| nesc1020 | BACFIRE, Minimal Cut Sets Common Cause Failure Fault Tree Analysis |
| nesc0767 | BEACON/MOD3, 1-D and 2-D 2 Phase Flow and Heat Transfer in Containment, LWR LOCA |
| iaea0820 | BLAST, Accident Conditions in Critical and Subcritical Thermal Reactor System |
| psr-0377 | BLOCKAGE2.5R, Plug of Emergency Core Cooling Suction Strainers by Debris BWR |
| ccc-0633 | BLT, Waste Transport through Porous Media from Container Failure |
| iaea0915 | BRA, Breast Radiation Analysis from Mammography |
| nea-0418 | BRUCH-D-06, LOCA of PWR Primary System with 23 Control Volume and 9 Rupture Points |
| 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 |
| nesc0435 | BURST-1, Rupture of 1-D Cylindrical Pressurized Liquid System, Hydrodynamic Calculation |
| nesc1080 | BWR-GALE, Radioactive Gaseous and Liquid Waste Release from BWR |
| ccc-0485 | BWR-LTAS, BWR Long Term Accident Simulation Program |
| nea-1313 | BWRDYN, Thermal Hydraulic Analysis of a BWR Plant |
| ccc-0476 | CAAC, System to Implement Atmospheric Dispersion Assessments |
| nea-1800 | CAFDATS, Converter of Angular Fluxes of DORT, ANISN and TORT Systems |
| ccc-0594 | CALKUX, Exposure Transmission of Medical X-Ray Beams Through Barrier Materials |
| ccc-0240 | CAMERA CAM, Radiation Dose Absorption by Computer Man |
| 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 |
| nea-0393 | CARNAC, Neutron Flux and Neutron Spectra in Criticality Accident |
| nea-0712 | CASSANDRE, 2-D Reactor Dynamic FEM Program with Thermohydraulic Feedback |
| nesc0548 | CEBUG, 3-D Transient Hydraulics for Na H2O Reaction by Finite Elements Method |
| ccc-0070 | CHARGE-2/C, Flux and Dose Behind Shield from Electron, Proton, Heavy Particle Irradiation |
| nea-0631 | CLAPTRAP, Pressure Transients in LWR Containment During LOCA |
| nesc0432 | COBRA, Transient Thermohydraulics Fuel Elements Clusters, Subchannel Analysis Method |
| nesc9978 | COBRA-3C/RERTR, Thermohydraulic Low Pressure Subchannel Transients Analysis |
| psr-0375 | COGAP, Nuclear Power Plant Containment Hydrogen Control System Evaluation Code |
| nesc0704 | COMCAN, Fault Tree Analysis, Minimal Cut Sets for Common Cause Failure |
| psr-0343 | COMIDA, Radionuclide Food Chain Model for Acute Fallout Deposition |
| ests0023 | COMPBRN3, Modelling of Nuclear Power Plant Compartment Fires |
| nesc0663 | COMRADEX-4, Doses from Radioactive Release, Meteorological Dispersion, Aerosol |
| ccc-0416 | CONDOS-II, Radiation Dose from Consumer Product Distribution Chain |
| nesc0433 | CONTEMPT, LWR Containment Pressure and Temperature Distribution in LOCA |
| nesc0818 | CONTEMPT-4/MOD5&6, LWR Containment Long-Term Pressure Distribution and Temperature Distribution in LOCA |
| nea-0567 | CORAN, PWR and BWR Containment Response to LOCA |
| nea-0333 | COSTANZA-RZ, 1-D Liquid Cooled Reactor Dynamic in R-Z Geometry |
| nea-0398 | COSTAX-BOIL, Transient Dynamic Analysis of BWR and PWR in Axial Geometry |
| nea-0533 | COSTAX-BWR, Coupled Time-Dependent 2 Group Neutron Diffusion and 2 Phase Fuel Rod Coolant Flow |
| ccc-0419 | CRAC2, Reactor Accident Risk Assessment |
| nea-1734 | CRISSUE-S, Neutronics/Thermal-hydraulics Coupling in LWR Technology |
| ccc-0518 | CRRIS, Health Risk Assessment from Atmospheric Releases of Radionuclides |
| nea-1535 | D2O, Computation of Thermodynamic and Transport Properties of Heavy Water |
| ccc-0455 | DEIS, Impact Measures of Low Level Radioactive Waste Disposal |
| nea-0840 | DENZ, Dense Toxic or Explosive Gases Dispersion in Atmosphere |
| nea-0453 | DEPCO-MULTI, Subcooled Decompression in PWR Primary System LOCA |
| ccc-0170 | DISDOS, Kerma in Model Man from External Gamma Source |
| ccc-0454 | DISPERS, Radioactive Release into Surface Water and Ground Water |
| nesc1146 | DORIAN, Bayes Method Plant Age Risk Analysis |
| ccc-0624 | DOSE-SGTR, Iodine Release During Steam Generator Tube Rupture (SGTR) in PWR |
| ccc-0536 | DOSEFACTOR-DOE, Dose Rate Conversion Factors for Photon and Electron Exposure |
| iaea0885 | DRUCK, Thermal, Mechanical Stress of PWR Fuel Rod During LOCA Blowdown |
| nea-0215 | DRUCKSCHALE-44, Pressure and Temperature Transients in Blowdown Accident |
| nea-0839 | DRUFAN-01/MOD2, Transient Thermohydraulics of PWR Primary System LOCA |
| nea-0457 | DRUGEVO, Time-Dependent Containment Pressure and Temperature in BWR or PWR LOCA |
| 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 |
| ccc-0383 | DWNWND, Downwind Atmospheric Concentration and Dispersion by Gaussian Plume Model |
| psr-0191 | EDISTR, Nuclear Data Base Generator for Internal Radiation Dosimetry Calculation |
| nea-0845 | EDO, Doses to Man and Organs from Reactor Operation Noble Gas and Liquid Waste Release |
| nesc0600 | EGAD, Ground Level Gamma Doses Function of Gamma Energy for Radioactive Releases |
| ccc-0119 | ELBA, Bremsstrahlung Dose from Isotropic Electron Flux on Plane Al Shield |
| nesc0546 | EMERALD, Radiation Release and Dose after PWR Accident for Design Analysis and Operation Analysis |
| nesc0685 | EMERALD-NORMAL, Routine Radiation Release and Dose for PWR Design Analysis and Operation Analysis |
| nea-0561 | ESDORA, Continuous and Instantaneous Fission Products Release into Atmosphere |
| 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 |
| iaea1273 | EXCURS-3-RR, Kinetics of Research Reactor Reactivity Transient Analysis |
| iaea0868 | FAPCO, Evaluation of Flaws in Nuclear Power Plant Component Structures |
| nesc1095 | FASTGRASS, Gaseous Fission Products Release in UO2 Fuel |
| nesc1092 | FIRAC, Nuclear Power Plant Fire Accident Model |
| nesc9597 | FLODIS, Thermal Response of FSV HTGR Core |
| nea-0669 | FONTA, Radiation Release in Atmosphere and Deposition in Human Organs |
| nesc0766 | FRANTIC-NRC, Accident Sequence and Event Tree Analysis for System Availability and Operation |
| nesc0694 | FRAP-S3 FRAP-S1, Steady-State LWR Oxide Fuel Elements Behaviour |
| nesc0658 | FRAP-T, Temperature and Pressure in Oxide Fuel During LWR LOCA |
| nesc0694 | FRAPCON2, Steady-State LWR Oxide Fuel Elements Behaviour, Fission Products Gas Release, Error Analysis |
| nesc0479 | FREADM-1, Reactor Kinetics Thermohydraulics Calculation for Fast Reactor Accidents |
| nea-0692 | FRELIB, Failure Reliability Index Calculation |
| nea-0982 | FRETA-B, LWR Fuel Rod Bundle Behaviour During LOCA |
| nesc9659 | FRTGEN, Fault Trees by Subtree Generator from Parent Tree for Program FTAP |
| nesc9659 | FRTPLT, Fault Tree Structure and Logical Gates Plot for Program FTAP |
| nesc0666 | FTA, Fault Tree Analysis for Minimal Cut Sets, Graphics for CALCOMP |
| 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 |
| ests0075 | GRASS-SST, Fission Products Gas Release and Fuel Swelling in Steady-State and Transients |
| ccc-0774 | GRSAC, Graphite Reactor Severe Accident Code |
| nea-1690 | GRTUNCL-3D/R-THETA-Z, Code to Calculate Semi Analytic First Collision Source and Uncollided Flux in an R-theta-Z grid |
| ccc-0721 | GRTUNCL3D, Code to Calculate Semi Analytic First Collision Source and Uncollided Flux (X, Y, Z) |
| nesc0443 | HAA3B, Heterogeneous Aerosol Transport after LMFBR Accidents, Lognormal Size Distribution |
| nesc0797 | HAARM, 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 |
| ccc-0452 | HADOC, External and Internal Organ Doses from Radiation Release at Hanford |
| nesc0710 | HAMOC, Pressure Transients in Reactor Vessel Piping System after Accidents |
| ccc-0387 | HARAD, Decay Isotope Concentration from Atmospheric Noble-Gas Release |
| nea-1125 | HEXANN-EVALU, Neutron Irradiation of Reactor Pressure Vessels |
| ests0545 | HGSYSTEM, Atmospheric Dispersion for Ideal Gases and Hydrogen Fluoride (HF) |
| ests1242 | HGSYSTEMUF6, Simulating Dispersion Due to Atmospheric Release of Uranium Hexafluoride (UF6) |
| nea-1169 | HORN, Fission Products Transport in Primary Coolant System of BWR and PWR in LOCA |
| ccc-0644 | HOTSPOT 3.0.1, Health Physics Code System for Evaluating Accidents Involving Radioactive Materials |
| nea-0499 | HYDY-B1, Channel Thermohydraulics During LOCA of BWR, PWR |
| nea-0216 | HYTRAN, Open Channel Thermal and Hydraulic Transients in LOCA |
| ests0005 | IMPACTS-BRC2.1, General Radiological Impacts Analysis |
| nesc0779 | IMPORTANCE, Minimal Cut Sets and System Availability from Fault Tree Analysis |
| iaea1378 | INDOSE V2.1.1, Internal Dosimetry Code Using Biokinetics Models |
| psr-0313 | INFLTB, Dosimetric Mass Energy Transfer and Absorption Coefficient |
| ccc-0185 | INREM-EXREM-3, Time-Dependent Organ Doses from Isotope Inhalation and Ingestion |
| nesc0590 | INTEG INSPEC, Accident Frequencies and Safety Analysis for Nuclear Power Plant |
| iaea0886 | INTERTRAN-I and INTERTRAN-II, Radiation Exposure from Vehicle Transport of Radioactive Material |
| ests0109 | IRDAM, Interactive Rapid Dose Assessment from Reactor Accident Effluents |
| ests0003 | IRRAS, Integrated Reliability and Risk Analysis System for PC |
| 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-1824 | KCUT, code to generate minimal cut sets for fault trees |
| nea-1865 | KICHE 1.3, Kinetics of Iodine Chemistry in the Containment of LWRs under Severe Accident Conditions |
| nea-1002 | KINE, 1-D PWR Dynamic with Partial Core Boiling |
| nesc0528 | KITT, Component and System Reliability Information from Kinetic Fault Tree Theory |
| ccc-0229 | KRONIC, Annual Body Tissue Dose from Continuous Atmospheric Release |
| psr-0277 | LEPRICON, PWR Vessel Dose Analysis with DORT and ANISN Program |
| nea-0860 | LISA, Hazard Assessment of Nuclear Waste Disposal in Geological Formations |
| nea-0623 | LOCA-MARK-2, Fuel Temperature and Clad Temperature in HWR Steam Generator LOCA |
| ccc-0385 | LPGS, Radiation Exposure from Radioactive Release into Hydrosphere |
| ccc-0064 | LPSC, Protons and Neutron Flux, Spectra Behind Slab Shield from Protons Irradiation |
| nea-1306 | LSHINSE, Air Scattering Neutron and Gamma Doserates for Complex Shielding Geometry |
| psr-0233 | LSL-M2, Neutron Spectra Log Adjustment for Dosimetry Applications |
| nea-1047 | MANYCASK, Radiation Dose Rate Around Many Casks |
| nesc0734 | MARCH, Containment Behaviour after LOCA, Blowdown, Meltdown, Metal H2O Reaction |
| ccc-0503 | MARINRAD, Health Hazard from Radioactive Material Release into Ocean |
| nesc0745 | MATADOR, Fission Products Release and Deposition in LWR Containment, Meltdown Accident |
| nea-0380 | MATRA, Void Simulation in Steam and H2O Mixture Channel in Accident |
| nea-1889 | MEGA, Mechanistic and Engineering Fission Gas Release Model for a Uranium Dioxide Fuel |
| nesc0700 | MELT-3, Thermohydraulics and Neutronics, Fast Reactor Transients with Feedback |
| ests0331 | MESORAD, 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 |
| nesc0653 | MOCUS, Minimal Cut Sets and Minimal Path Sets from Fault Tree Analysis |
| psr-0411 | MORECA, Simulating Modular High-Temperature Gas Cooled Reactor Core Heatup |
| nesc0508 | MUCHA1, Fuel Rod Pair Thermohydraulics During LOCA and ECCSA for LWR |
| nesc0508 | MUCHA2, Primary Coolant Thermohydraulics During LOCA and ECCS for LWR |
| nea-0933 | MULTI-KENO, Criticality Safety Analysis by Monte-Carlo |
| nea-1041 | MULTIPLET, Large Event Trees for Risk Assessment Calculation |
| ccc-0164 | NAC, Neutron Activation Analysis and Isotope Inventory |
| nesc0717 | NAHAMMER, Pressure Transients in Na LMFBR Piping System, Linear Fluid Hammer Theory |
| nea-0806 | NAIAD, LOCA Transient and Steady-State 2 Phase Flow in Channel Network |
| nesc0780 | NALAP, Thermohydraulics for Na Cooled LMFBR after Pipe Rupture and Accidents |
| nesc0719 | NATRAN-2, LMFBR Piping System Pressure Transients, Fluid Hammer and Na H2O Reaction |
| nesc0718 | NATRANSIENT, LMFBR Piping System Pressure Transients, Fluid Hammer, Na H2O Reaction |
| nea-0853 | NAUA-MOD5 NAUA-MOD5/M, Aerosols in Reactor Containment During Meltdown |
| nea-1635 | NIRAD, A Two-Dimensional Radiation Hydrodynamics Code |
| nea-0671 | NORCOOL, BWR LOCA Analysis with Thermal Non-Equilibrium and Counter Current Flow |
| nea-0921 | NOTAM, Neutronics Hydraulics of BWR in Steady-State Conditions |
| 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 |
| nesc9888 | NUTRAN, Doses by Radionuclide Migration from Nuclear Waste Storage |
| nesc1125 | OCA-P, PWR Vessel Probabilistic Fracture Mechanics |
| nesc0898 | OCTAVIA, PWR Pressure Vessel Failure Probability for Routine Pressure Transients |
| nea-1249 | ORION-II, Concentration and Dose from Radioactive Release into Atmosphere |
| nesc0555 | PARET-ANL(NESC), Thermohydraulics of Reactivity Accident in LWR |
| psr-0516 | PARET-ANL, Code System to Predict Consequences of Nondestructive Accidents in Research and Test Reactor Cores |
| ccc-0499 | PART61, Low Level Radioactive Waste Impact Analysis |
| 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-ESTSC, Radioactive Dose Assessment and NRC Verification |
| psr-0432 | PHAZE, Parametric Hazard Function Estimation |
| nea-1084 | PIEDEC, Effective Dose Equivalent from Inhalation or Ingestion |
| 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 |
| nea-0704 | PLUMEX, Gamma Doses from Atmospheric Plume |
| nea-0904 | PRECIP-2, Zircaloy Cladding Oxidation Simulation for LWR under LOCA Conditions |
| nesc0528 | PREP KITT, System Reliability by Fault Tree Analysis |
| nesc0528 | PREP, Min Path Set and Min Cut Set for Fault Tree Analysis, Monte-Carlo Method |
| nea-0251 | PREST, Pressure Temperature Transients, I Inhalation in Containment Building from LOCA |
| nea-0695 | PROCIV, Protection Coefficient from Fallout in Residential Area Housing |
| nesc0778 | PROSA-1 PROSA-2, Accidents Probability Analysis Using Response Surface Method |
| 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 |
| ccc-0556 | QUINCE, Dose Absorption, Health Risk from Skin Contamination |
| ests0062 | RABFIN PARTS, Noble Gas, Iodine, Particulate Gaseous Effluent Dose Parameters |
| ccc-0422 | RADRISK, Doses to Human Organs and Health Effects from Inhalation and Ingestion |
| ccc-0800 | RADTRAD 3.03, Model for Radionuclide Transport and Removal and Dose Estimation |
| nesc0889 | RAS, Fault Tree Analysis, Reliability, Minimal Cut Sets for Common Cause Failure |
| ccc-0783 | RASCAL 4.2, Radiological Doses from Accidental Release to Atmosphere |
| ests0050 | RATAF, Radioactive Liquid Tank Failure |
| ccc-0632 | RBD, Doses from Radionuclide Inhalation, Ingestion, Wound Uptake from Bioassays |
| nesc1090 | RCSLK9, PWR Coolant System Leak Rate |
| iaea0846 | REBEL-3, Whole Body and Organ Gamma Doses of Inhomogeneous Phantom by Monte-Carlo |
| nesc0369 | RELAP-4, Transient 2 Phase Flow Thermohydraulics, LWR LOCA and Reflood |
| nesc0917 | RELAP-5, Transient 2 Phase Flow Thermohydraulics, LWR LOCA Accidents |
| nea-0437 | RELAP-UK, Thermohydraulic Transients and Steady-State of LWR |
| nea-0821 | RELAP/REFLA, Core Reflooding During PWR LOCA |
| nesc0733 | RELAP3B/MOD110, Flow Temperature Pressure Steam Quality in LWR after LOCA and Accidents |
| nea-0615 | RELOSS, Reliability of Safety System by Fault Tree Analysis |
| ests0579 | REMIT, Radiation Exposure Monitoring and Information Transmittal System |
| nea-0429 | REMO, Failure Analysis of System with Reparable and Standby Components by Monte-Carlo |
| ccc-0786 | RESRAD 6.5, Residual Radioactive Material Guideline Implementation |
| ests1225 | RESRAD-BUILD2.36, Residual Radioactive Material Guideline Implementation |
| iaea1286 | RETRAC, Reactor Core Accident Simulation |
| ccc-0137 | RIBD, Fission Products Inventory and Delay Heat in Fast Reactors, with Data Library |
| nea-1825 | RIMACS, Reactor Inspection Main Control System |
| ccc-0486 | RISKAP, Risk Assessment of Radiation Exposure for Population |
| ccc-0623 | RISKIND, Radiological Risk Assessment for Spent Nuclear Fuel Transportation |
| nesc0265 | RSAC, Gamma Doses, Inhalation and Ingestion Doses, Fission Products Inventory after Fission Products Release |
| 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 |
| ccc-0834 | SCALE 6.2.3, A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design |
| nea-1755 | SCIP, Radioactive Surface Contamination Investigation Program |
| nea-0498 | SCORCH-B2, BWR Core Heating During LOCA |
| ests0015 | SCORE-EVET, 3-D Hydraulic Reactor Core Analysis |
| nea-1540 | SCRELA, LOCA Analysis of Super-Critical Light-Water Reactors |
| nea-0865 | SCRIMP, Steady-State Thermohydraulics of HTGR Subchannel |
| ccc-0620 | SEECAL-2.0, Specific Effective Energy in Human Body Due to Radiation |
| nesc1063 | SEISIM-1, Seismic Probabilistic Risk Assessment |
| ccc-0310 | SFACTOR, Dose Equivalent to Target Organs from Radionuclides in Organs |
| ccc-0379 | SHIELDOSE, Doses from Electron and Proton Irradiation in Space Vehicle Al Shields |
| nea-0538 | SHOSPA-MOD, Hot Spot Factors for Fuel and Clad, Hot Channel Factors |
| ccc-0118 | SIGMA/B, Doses in Space Vehicle for Multiple Trajectories, Various Radiation Source |
| nesc1082 | SIGPI, Probabilistic System Performance by Fault-Tree Analysis |
| nea-1570 | SITE-94, Biosphere Model for SKI Project on the island of Aspro |
| ccc-0289 | SKYSHINE, Dose Rate Outside Concrete Steel Building from 6 MeV Gamma by Monte-Carlo |
| ccc-0646 | SKYSHINE-KSU, Gamma Skyshine Doses by Integral Line-Beam Method |
| ccc-0704 | SLIDERULE 1.0,Slide Rule for direct radiation exposure approximation in criticality accidents |
| nea-1046 | SMART, Radiation Dose Rates on Cask Surface |
| ccc-0602 | SMART-BNL, Offsite Radionuclide Air Concentration from Reactor Accident |
| nesc0559 | SOFIRE-2, Containment Temperature and Pressure During Na Pool Fire, 1-Cell or 2-Cell Analysis |
| psr-0174 | SORA, Radionuclide Analysis Data Storage and Retrieval |
| nea-0187 | SOREX-1, Worst Accident Simulation in Sora Pulsed Fast Reactor |
| ccc-0120 | SPACETRAN, Radiation Leakage from Cylinder with ANISN Flux Calculation |
| nea-1165 | SPEEDI,EXPRESS, Radiation Dose from Plume Release in Nuclear Accident |
| ests0054 | SPIRT, Stress Strains from Transient Pressure |
| 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 |
| ests1052 | SQUIRT, Seepage in Reactor Tube Cracks |
| nea-0684 | SSYST, Modular System for Transient Fuel Rod Behaviour Under Accident Condition |
| nea-0575 | STESTA, Steady-State State-Variable Profiles of Thermohydraulic Piping System |
| nea-0993 | STRADE, Stratified Random Design for Reactor Safety Analysis |
| nesc0924 | SUBDOSA, External Gamma, Beta Doses from Radionuclide Release into Atmosphere |
| 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 |
| psr-0308 | TAM3, Monte-Carlo Sensitivity and Uncertainty Analysis of Radium in Lake Contamination Model |
| nea-1328 | TERFOC-N, Radiation Doses in Food Chain from Atmospheric Release |
| iaea1272 | THACT-RR, Analysis of Thermal Hydraulics Transients in Research Reactor Core |
| nea-0774 | THALES, Thermohydraulic LOCA Analysis of BWR and PWR |
| nesc0512 | THETA-1B, Fuel Rod Temperature Distribution by 2-D Diffusion, Heat Transfer to Coolant, LWR LOCA |
| nea-0778 | THYDE-B2, Thermohydraulic Transients During LOCA of BWR |
| nea-0779 | THYDE-P, PWR LOCA Thermohydraulic Transient Analysis |
| nea-1592 | TIBSO, Nuclear Transitions and Radioactivity Migration in Technological System |
| nea-0701 | TIRION-4, Atmospheric Dispersion of Radioactive Materials for Various Weather Conditions |
| nesc1093 | TORAC, Flows, Pressure, Materials Transport within Structure During Tornado |
| nesc9710 | TOXRISK, Toxic Gas Release Accident Analysis |
| nesc0836 | TRAC, Thermohydraulics, Reactor Kinetics, 2 Phase Flow LOCA Analysis |
| nesc1031 | TRAC-BD1, LOCA Analysis of BWR with 3-D Pressure Vessel and Multi Bundle Fuel Model |
| nea-1593 | TRAC-PF1/EN MOD 3, Best Estimate Coupled 3-D Neutronics-Thermalhydraulics |
| nea-1291 | TRANS-ACE, Radioactive Materials Transport in Reprocessing Plant Fire Accident |
| nesc0268 | TRANS-FUGUE-1, Single Channel 2 Phase Flow Heat Transfer after Boiling |
| iaea1209 | TRANSV2, LOCA and Steady-State Thermohydraulic Analysis of MTR |
| nea-0745 | TRAPSCO-2, Pressure and Temperature Transients in PWR Subcompartments During LOCA |
| nesc1028 | TRIPM, Isothermal Transport and Decay of Radionuclides in Aquifer |
| iaea1337 | TRISTAN-IJS, Steady-State Axial Temperature and Flow Velocity in Triga Channel |
| nesc0712 | TWODEE-2/MOD3, 2-D Time-Dependent Fuel Elements Thermal Analysis after PWR LOCA |
| nesc0824 | UDAD, Radiation Exposure to Man at Uranium Processing Plant |
| 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 |
| nea-0610 | WEERIE, Radioactive Release from Reactor to Cooling Circuit and Atmosphere |
| nesc0278 | WHAM-6, Pressure and Velocity Transients in Fluid Pipes, Wave Superposition Method |
| ccc-0427 | WRAITH, Internal and External Doses from Atmospheric Release of Isotopes |
| nea-0401 | ZOCO-6, Temperature Transients in BWR and PWR Containment During LOCA |
| nea-1251 | ZYLIND, Gamma Penetration for Cylindrical Source and Shield Geometry |
| iaea0867 | ZZ IRDF-2002, 640-Group Cross-Section Library and Spectra for Dosimetry Calculation in ENDF-6 Format |
| iaea0867 | ZZ IRDF-2002-ACE, Cross-Section Library and Spectra for Dosimetry Calculation in ACE Format for Monte Carlo methods |
| iaea0867 | ZZ IRDF-82, 620-Group Cross-Section Library and Spectra for Dosimetry Calculation in ENDF-5 Format |
| iaea0867 | ZZ IRDF-90, 640-Group Cross-Section Library and Spectra for Dosimetry Calculation in ENDF-6 Format |