Online Catalog
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Click on RSICC Tapelist to view list of files distributed with package.

Note: RESTRICTIONS APPLY TO SOME PACKAGES -
810 -- US DOE 10CFR810 Jurisdiction
FEDC -- US Government Agencies and Their Contractors Only
OECD -- Restricted/See Abstract
USSO -- US Distribution Only
USUNV -- US Universities Only
Packages starting with R
Package NameAbstractRSICC TapelistTitle
RABFIN PARTSAbstractC00668 IBMPC 00Code System for Calculating Gaseous Effluent Dose Parameters.
RACCAbstractC00388 CY000 00A Code System for Computing Radioactivity-Related Parameters for Fusion Reactor Systems.
RACCAbstractC00388 I3033 00A Code System for Computing Radioactivity-Related Parameters for Fusion Reactor Systems.
RACC-PULSEAbstractC00639 MNYWS 00RACC Code System for Computing Radioactivity-Related Parameters for Fusion Reactor Systems Modified for Pulsed/Intermittent Activation Analysis.
RACERAbstractC00174 U1108 00Calculation of Potential External Dose from Airborne Fission Products Following Postulated Reactor Accident.
RAD 2AbstractC00122 I7090 00Fission Product Radioactivities Calculation.
RADACAbstractC00627 PC486 02Code System for Calculating Radioactive Decay and Accumulation of Decayed Products Using Integer-Array Arithmetic for Precise Evaluation of the Bateman Equations.
RADAKAbstractP00122 I0360 00Flux Spectra Unfolding Code System - Neutron or Gamma-Ray Detectors.
RADCOMPT 2.10LAbstractP00348 IBMPC 00Sample Analysis Code System for the Dual Channel Counter.
RADDECAY 4.02AbstractD00134 IBMPC 03Radioactive Decay Data for Radiological Assessments.
RADHEAT-V4AbstractC00300 FM380 00A Code System To Generate Multigroup Constants and Analyze Radiation Transport for Shielding Safety Evaluation.
RADOSAbstractC00088 I3675 00Gamma-Ray Dose Estimation from Cloud of Radioactive Gases by Kernel Integration.
RADRISKAbstractC00422 DGMV1 00Estimates Radiation Doses and Health Effects from Inhalation or Ingestion of Radionuclides. See C00476/CAAC.
RADRISKAbstractC00422 I3033 00Estimates Radiation Doses and Health Effects from Inhalation or Ingestion of Radionuclides. See C00476/CAAC.
RADSHIP-2AbstractC00523 FM200 00Code System To Analyze Radiological Impact From Radwaste Transportation.
RADSYSAbstractC00530 I3033 00Code System for Radioactivity Buildup and Radioactive Waste Generation Calculations.
RADTRAD 3.03AbstractC00800 IBMPC 00A Simplified Model for RADionuclide Transport and Removal And Dose Estimation.
RADTRAD 3.03-EXEAbstractC00800 IBMPC 01A Simplified Model for RADionuclide Transport and Removal And Dose Estimation.
RAFFLE/2AbstractC00279 C0176 00A General Purpose Monte Carlo Code System for Neutron Transport with Mixed Zone Geometry Option.
RAFFLE/2 MOD 2AbstractC00279 I0360 00A General Purpose Monte Carlo Code System for Neutron Transport with Mixed Zone Geometry Option.
RAIDAbstractC00083 I7090 00Monte Carlo Multibend Duct Shielding Code.
RANCHMDAbstractC00589 D8810 00Radionuclide Chain Transport with Matrix Diffusion.
RAPIDAbstractC00797 PCX86 00RAdial Power and Burnup Prediction by Following Fissile Isotope Distribution in the Pellet.
RASC-2DAbstractC00318 I0370 00Two-Dimensional Removal Diffusion Code Reactor Shielding Design Code System.
RASCAL 4.3AbstractC00783 PCX86 02Radiological Assessment Systems for Consequence AnaLysis.
RASPAAbstractC00352 C7600 00A Code for the Calculation of Buildup and Decay of Fission Products and Actinides.
RATAFAbstractC00681 IMFPC 01Code System for the Radioactive Liquid Tank Failure Study.
RBDAbstractC00632 IBMPC 00U.S. Army Radiological Bioassay and Dosimetry.
RCSLK9AbstractP00452 IBMPC 00Code System to Calculate Reactor Coolant System Leak Rate.
RDMMAbstractP00598 I0360 00Flux Spectra from In-Pile Fast Neutron Activation Experiment.
REAC*3AbstractC00443 IBMPC 00Computer Code System for Activation and Transmutation.
REAC*3AbstractC00443 MFMWS 00Computer Code System for Activation and Transmutation.
REACTIONAbstractP00347 AL000 00Code System to Calculate Integral Parameters with Reaction Rates from WIMS Output.
REACTIONAbstractP00347 IBMPC 00Code System to Calculate Integral Parameters with Reaction Rates from WIMS Output.
REACTORSHIELDING-NMSAbstractM00014 MNYCP 00REACTORSHIELDING-NMS, Reactor Shielding for Nuclear Engineers.
REBEL 3AbstractC00299 I0360 00Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms.
REBEL-2AbstractC00299 ICL00 00Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms.
REBEL-2AbstractC00299 C6600 00Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms.
REBUS3/VARIANT8AbstractC00653 MNYWS 01Code System for Analysis of Fast Reactor Fuel Cycles.
REBUS-PC 1.4AbstractC00708 PC586 00Code System for Analysis of Research Reactor Fuel Cycles.
RECAPAbstractP00414 IBMPC 00Replacement Energy Cost Analysis Package.
RECAPAbstractP00414 IBMPC 01Replacement Energy Cost Analysis Package.
RECOILAbstractD00055 I3033 01Multigroup Primary Recoil Spectra, Displacement Rates and Gas-Production Rates for Radiation Damage Studies.
REDIFFUSIONAbstractC00347 I0360 00One-Dimensional Neutron Removal-Diffusion and Gamma-Ray Kernel Integration or Diffusion Theory Calculator.
REEX-1AbstractP00599 I0370 00U, Pu, Nitric Acid Distribution in Counter Current Pluristage Stripping.
REFCO83AbstractP00447 I3033 00Nuclear Fuel Cycle Cost Economics Code System.
REFERDOUAbstractP00249 FM380 00Code System for NE-213 Unfolding of Neutron Spectra up to 100 MeV with Response Function Error Propagation.
REFIT-2009AbstractC00775 PCX86 00Multilevel Resonance Parameter Least Square Fit of Neutron Transmission, Capture, Fission & Self Indication Data.
REFLUXAbstractP00403 I3033 00Code System to Predict LWR Reflood Heat Transfer.
REFREPAbstractC00570 D8810 00A Near-Field Model For A Spent Fuel Repository.
REFUM-BROADAbstractP00039 F2307 00Monte Carlo Codes for Calculating Efficiencies and Response Functions of NaI(Tl) Crystals for Thick Disk Gamma-Ray Sources.
REGNAbstractP00165 I0360 00Code System for Solving Nonlinear Systems of Equations via the Gauss-Newton Method.
RELAP3B/MOD110
810
AbstractP00422 C7600 00Reactor System Transient Code.
RELAP4/MOD7/101
810
AbstractP00416 C0176 00Best Estimate Code System to Calculate Thermal & Hydraulic Phenomena in a Nuclear Reactor or Related System.
RELAP5/MOD1/029
810
AbstractP00423 C0176 00Thermal Hydraulic Computer Code System.
RELAP5/MOD1/029_EXE
810
AbstractP00423 C0176 01RELAP5/MOD1/029_EXE_only
REMIT 5.1AbstractP00482 IBMPC 01Radiation Exposure Monitoring and Information Transmittal System.
REPCAbstractP00195 C0000 00Estimation of Nuclear Reaction Effects in Proton-Tissue-Dose Calculations.
REPRISK PC 1.02AbstractC00586 PC386 01Repository Risk Assessment Software for Personal Computers.
RESENDDAbstractP00215 C0740 00A Code System for Reconstruction of Resonance Cross Sections from Evaluated Nuclear Data in ENDF/B Format.
RESENDDAbstractP00215 D0780 00A Code System for Reconstruction of Resonance Cross Sections from Evaluated Nuclear Data in ENDF/B Format.
RESPMGAbstractP00060 I0360 00Response Matrix Generation Code System.
RESRAD 6.5AbstractC00786 PCX86 00Code System to Implement Residual Radioactive Material Guidelines, and RESRAD-BUILD 3.0.
REST 1;2;3AbstractC00225 I0360 00Fission Product Inventory Code System with Fission Product Escape Model.
RETRACAbstractC00635 D0VAX 00Code System for the Analysis of Material Test Reactor (MTR) Cores.
RETRANSAbstractC00669 SUN05 00Code System For Calculating Reactivity Transients In a LWR.
REX2-87AbstractP00290 D8810 00A Code For Calculating Self-Shielded Multigroup Neutron Cross Sections and Self-Shielding Factors From Preprocessed ENDF/B Basic Data Files.
RFSP-JULAbstractP00126 I0360 00Unfolding Code System for Neutron Spectra Evaluation from Activation Data.
RFUNCAbstractP00312 D0VAX 00Code System to Analyze Differential Scattering Data.
RGENDFAbstractP00239 C0170 00Format Translation from NJOY GENDF Format to ENDF/B-V and Other Formats.
RHEINAbstractC00585 I3090 00Reactor Code System for Neutron Physics Calculation.
RIBD-IIAbstractC00137 C6600 00Radioisotope Buildup and Decay Code System.
RIBD-IIAbstractC00137 I0360 00Radioisotope Buildup and Decay Code System.
RIBD-IRTAbstractC00382 U1100 00Radioisotope Buildup and Decay Code System.
RICANTAbstractC00569 D8810 00A Computer Code for 2-D Transport Calculations in x-y Geometry Using the Interface Current Method.
RICEAbstractP00022 I0360 00A Program to Calculate Primary Recoil Atom Spectra from ENDF/B Data.
RICECCCAbstractC00348 I0360 00A Reactor Nuclide Inventory Code for Calculating Actinides and Fission Products.
RICMAbstractP00600 I0360 00Resonance Absorption in Multi-Region Slab or Square or Hexagonal Lattice.
RIPPLEAbstractP00571 CYXMP 00A Computer Program for Incompressible Fluid Dynamics with Free Surfaces.
RISKAPAbstractC00486 I3033 00Analysis of Increased Risk to Arbitrary Populations.
RISKIND 2.0
FEDC
AbstractC00623 IBMPC 02Radiological Risk Assessment Code System for Spent Nuclear Fuel Transportation.
RITTSAbstractD00011 I0360 00121-Group Coupled Neutron and Gamma-Ray Cross-Section Data for Transport Codes.
RIVER-RADAbstractC00626 MNYCP 00Code System for Simulating the Transport of Radionuclides in Rivers.
RMET21AbstractC00597 D0VAX 00Detailed Space and Energy Treatment of Neutron Resonances for Homogeneous Mixtures and Cylinderized Reactor Cells.
RNGPAbstractP00066 I3675 00Random Number Generator Package.
ROCKWELL-RSDMAbstractM00017 MNYCP 00Reactor Shielding Design Manual by Rockwell T. III.
ROLAIDS-CPMAbstractP00353 SUN04 00Code System to Calculate Group-Averaged Cross Sections Using the Collision Probability Method.
RRRAbstractC00196 I0360 00Radiation Transport in Air-Analysis of Routine Releases of Short-Lived Radioactive Nuclides.
RSAC6.2AbstractC00125 PC586 03Radiological Safety Analysis Code System.
RSAC-7.2AbstractC00761 PC586 01Radiological Safety Analysis Code System.
RSYSTAbstractC00269 I0360 00Integrated Modular Code System for Shielding and Reactor Physics Calculations.
The Radiation Safety Information Computational Center (RSICC) is a Department of Energy Specialized Information Analysis Center (SIAC) authorized to collect, analyze, maintain, and distribute computer software and data sets in the areas of radiation transport and safety. RSICC resides in the Reactor and Nuclear Systems Division (RNSD) at Oak Ridge National Laboratory.