Computer Programs

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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 |

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 |

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 |

nesc9978 | COBRA-3C/RERTR, Thermohydraulic Low Pressure Subchannel Transients Analysis |

nesc0432 | COBRA-4I, Transient Thermohydraulics Fuel Elements Clusters, Subchannel Analysis Method |

psr-0375 | COGAP, Nuclear Power Plant Containment Hydrogen Control System Evaluation Code |

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 |

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 |

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 |

nea-1904 | INES-CLASS, assessment of accidents significance occurred at nuclear facilities |

psr-0313 | INFLTB, Dosimetric Mass Energy Transfer and Absorption Coefficient |

ccc-0185 | INREM-EXREM-3, Time-Dependent Organ Doses from Isotope Inhalation and Ingestion |

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 |

nea-0806 | NAIAD, LOCA Transient and Steady-State 2 Phase Flow in Channel Network |

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-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 |

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 |

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 |

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 |

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 |

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 |