Online Catalog
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Click on Abstract to read the package abstract.
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
RUGA -- Restricted Use Government Authorized
USSO -- US Distribution Only
USUNV -- US Universities Only
Packages starting with O
Package NameAbstractRSICC TapelistTitle
O5RAbstractC00017 I3675 00A General-Purpose Monte Carlo Neutron Transport Code System.
O5SAbstractP00014 DP010 00Response Function Generator--An O5R Monte Carlo Code for Calculating Pulse Height Distributions Due to Monoenergetic Neutrons Incident on Organic Scintillators.
O5SAbstractP00014 I3675 00Response Function Generator--An O5R Monte Carlo Code for Calculating Pulse Height Distributions Due to Monoenergetic Neutrons Incident on Organic Scintillators.
O6RAbstractC00128 I3675 00A General-Purpose Monte Carlo Transport Code System.
OCA-PAbstractP00392 I3033 00Pressure Vessel Fracture-Mechanics Code System.
OCA-PAbstractP00392 IBMPC 00Pressure Vessel Fracture-Mechanics Code System.
OCTAVIAAbstractP00460 I0370 00Code System to Calculate Pressure Vessel Failure Probabilities.
OGREAbstractC00046 I3675 00A General-Purpose Monte Carlo Gamma-Ray Transport Code System.
OGRE-MINAbstractC00409 DGECL 00A General-Purpose Monte Carlo Gamma-Ray Transport Code System for Minicomputers.
OMCOSTAbstractP00381 I3033 00Code System for Non-fuel O & M Cost Estimation for Large Steam-Electric Power Plants.
OMEGAAbstractC00433 BESM6 00Monte Carlo Criticality Code System.
ONETRANAbstractC00266 C7600 00A One-Dimensional Multigroup Discrete Ordinates Finite Element Transport Code System.
ONETRANAbstractC00266 CY000 00A One-Dimensional Multigroup Discrete Ordinates Finite Element Transport Code System.
ONETRANAbstractC00266 I3033 00A One-Dimensional Multigroup Discrete Ordinates Finite Element Transport Code System.
OOSIIAbstractC00324 C0000 00Calculation of Isotropic Scattering by Particles for One-Dimensional and Three-Dimensional Transport in Slabs by Invariant Imbedding, Orders-of-Scattering Method, Including Check Calculations by Integral Transport Theory and Monte Carlo.
OPERATIONAL MONTE CARLO GUIAbstractP00619 PCX86 01Operational Monte Carlo GUI (OMG)
OPEX-IIAbstractC00103 I7090 00Radiation Shield Optimization Code.
OPTIMAbstractC00817 I0370 00Minimization of Band-Width of Finite Elements Problems.
ORCENT-2AbstractP00474 I3033 00Code System for Analysis of Steam Turbine Cycles Supplied by Light Water Reactors.
ORESUNDAbstractD00267 MNYCP 00Nordic Mesoscale Dispersion Experiments over Land-Water-Land.
ORIGEN2.2AbstractC00371 ALLCP 03Isotope Generation and Depletion Code - Matrix Exponential Method.
ORIGEN-JENDL32AbstractC00703 MNYWS 00Isotope Generation and Depletion Code - Matrix Exponential Method.
ORINC
USSO		AbstractP00439 I0360 00Code System for 1-D Implicit Heat Conduction Solution.
ORION-IIAbstractC00491 FM780 00A Computer Code to Estimate Environmental Concentration and Dose Due to Airborne Release of Radioactive Material.
ORIP_XXIAbstractC00731 PC586 02Computer Programs for Isotope Transmutation Simulations.
ORLIBJ32AbstractD00255 MNYCP 00ORIGEN2 Libraries Based on JENDL-3.2.
ORMDIN
USSO		AbstractP00399 I3033 002-D Nonlinear Inverse Heat Conduction.
ORMGEN3DAbstractP00430 CY0MP 00Mesh Generator for 3-D Crack Geometries.
ORMONTEAbstractP00275 IBMPC 00Uncertainty Analysis Code System for Use with User-Developed Systems Models.
ORPHEE VIAbstractC00159 I3675 00Kernel Integration Code System - Attenuation of Fast Neutrons in Cylindrical Layers of Water and Dense Material.
ORPLOT-PCAbstractP00328 PC386 00Plotting Package for Data Evaluation Intercomparison.
ORSMAC
USSO		AbstractP00437 I3033 00Code System to Calculate Fluid Circulation Patterns Near Jets.
ORTHIS-ORTHATAbstractP00569 I0360 00ORTHIS: Steady-State Heat Conduction in 2-D X-Y, R-Z and R-Theta Geometry; ORTHAT: Transient Heat Conduction in 2-D X-Y, R-Z and R-Theta Geometry.
ORTURBAbstractP00418 I0360 00HTGR Steam Turbine Dynamic Behavior.
ORYX-EAbstractD00038 I0360 00ORIGEN Yields and Cross Sections Nuclear Transmutation and Decay Data from ENDF/B-IV.
ORYX-EAbstractD00038 I0360 01ORIGEN Yields and Cross Sections Nuclear Transmutation and Decay Data from ENDF/B-IV.
OZMAAbstractC00406 I0370 00Calculation of Resonance Reaction Rates in Reactor Lattices Using Resonance Profile Tabulations.
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The Radiation Safety Information Computational Center (RSICC) collects, analyzes, maintains, and distributes software in the areas of radiation transport and safety. RSICC resides in the Nuclear Energy and Fuel Cycle Division (NEFCD) at Oak Ridge National Laboratory.