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-4MOD3, 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 2.07.1, Field Evaluation of Radiation Release from Nuclear Accident
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
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 4.1, 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
ccc-0785	SCALE 6.1.2, Modular system for criticality, shielding, source term, fuel depletion/decay, inventories, reactor physics
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-0522	VARSKIN 3 V3.1.0, Dose Calculation for Skin Contamination, with Sadde Input Generator
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
dlc-0069	ZZ ACTL82, Data Library of Evaluated Activation Cross-Sections
nea-0886	ZZ AMPX-2/123, 123-Group Neutron Cross-Section Library from ENDF/B-4 by AMPX-2
nea-0886	ZZ AMPX-2/219, 219-Group Neutron Cross-Section Library from ENDF/B-4 by AMPX-2
iaea0949	ZZ BROND, Evaluated Neutron Data Library in ENDF-6 Format
dlc-0030	ZZ DECAYREM/C, Decay Spectra Library for EXREM Calculation
dlc-0010	ZZ DLC-10B AVKER, Neutron Kerma Response Function Data Library
dlc-0011	ZZ DLC-11 RITTS, 121-Group Coupled Cross-Section for ANISN, DOT, MORSE
dlc-0014	ZZ DLC-14 AIR, Group Constant Library of Secondary Gamma Transport in Air for ANISN Calculation
dlc-0017	ZZ DLC-17 NOX, 119-Group Coupled Cross-Section of Nitrogen, Oxygen, Air for MORSE
dlc-0090	ZZ DOSCOV, 24-Group Covariance Data Library from ENDF/B-V for Dosimetry Calculation
dlc-0079	ZZ DOSDAT-2, Gamma and Electron Dose Conversion Factor Data Library for Body Organs
dlc-0144	ZZ DOSEDAT-DOE, Dose-Rate Conversion Factors for External Photon, Electron Exposure
dlc-0080	ZZ DRALIST, Radioactive Decay Data for Dosimetry and Hazard Assessment
dlc-0167	ZZ FGR-DOSE, Dose Coefficient for Intake and Exposure to Radionuclides
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
dlc-0128	ZZ LAHIMACK, Multigroup Neutron and Gamma Cross-Section and Response Function up to 800 MeV
dlc-0172	ZZ NUCDECAY, Nuclear Decay Data for Radiation Dosimetry Calculation for ICRP and MIRD
dlc-0134	ZZ RADDECAY, Decay Data Library for Radiological Assessment
dlc-0055	ZZ RECOIL/B, Heavy Charged Particle Recoil Spectra Library for Radiation Damage Calculation
dlc-0093	ZZ SKYPORT, Importance Function for Neutron and Gamma for Skyshine Dose from Accelerator
dlc-0188	ZZ SKYSDATA-KSU, Neutron and Gamma Skyshine Responses
dlc-0178	ZZ SNLRML, Dosimetry Cross-Section Recommendations
dlc-0164	ZZ UNGER, Effective Dose Equivalent Data for Selected Isotopes