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 |
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 |
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 |
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 |