Online Catalog
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Packages starting with G
Package NameAbstractRSICC TapelistTitle
G33-GPAbstractC00494 IBMPC 01Kernel Integration Code System - Multigroup Gamma-Ray Scattering Using the GP Buildup Factor.
G3-6EDAbstractC00075 C6600 00Kernel Integration Code System - Multigroup Gamma Ray Scattering.
G3-6EDAbstractC00075 I3033 00Kernel Integration Code System - Multigroup Gamma Ray Scattering.
GABASAbstractP00175 U1108 00A Code System for Generating Composite Time-Dependent Fission Produce Spectra.
GADJETAbstractC00115 C6600 00Monte Carlo Gamma-Ray Adjoint Energy Transport Code in Complex Three-Dimensional Geometry.
GAINCALBAbstractP00056 I0360 00Determination of the Gain Used with Organic Scintillation Detect.
GAKER-KIRAAbstractC00813 C3600 00Energy Transfer of Protons in H2O or Polyethylene and Deuterons in D2O.
GALAXY-6AbstractP00098 I0370 00Neutron Multigroup Cross Section Processor.
GALE BWRAbstractC00335 U1100 00Boiling Water and Pressurized Water Reactors Gaseous and Liquid Effluents Radiological Assessment Code System.
GALE PWR & BWRAbstractC00335 I3033 00Boiling Water and Pressurized Water Reactors Gaseous and Liquid Effluents Radiological Assessment Code System.
GALE86AbstractC00506 MNYCP 02Calculation of Routine Radioactive Releases in Gaseous and Liquid Effluents from Boiling Water and Pressurized Water Reactors.
GAMANAbstractP00083 DP010 00Qualitative and Quantitative Evaluation of Ge(Li) Gamma-Ray Spectra.
GAMANALAbstractP00506 D0VAX 00Code System for Computerized Quantitative Analysis By Gamma-Ray Spectrometry.
GAMDAT-78AbstractD00083 I0370 00Library of Gamma-Ray Decay Data for 2055 Radionuclides.
GAMIDENTAbstractP00154 C0000 00A Program to Aid in the Identification of Unknown Materials by Gamma-ray Spectroscopy.
GAMLEG-75AbstractP00086 C7600 00Multigroup Cross Section Generator for Photon Transport Calculations.
GAMLEG-JRAbstractP00116 F2307 00Multigroup Cross-Section Generator for Photon Transport Calculations.
GAMLEG-JRAbstractP00116 I3033 00Multigroup Cross-Section Generator for Photon Transport Calculations.
GAMLIBAbstractD00006 I0360 0099-Group Neutron Cross Sections for Use in the GAM Portion of the GGC Multigroup Cross Section Code.
GAMMAAbstractP00095 I0360 00Monte Carlo Code System for Calculating Efficiencies and Response Functions of NaI(Tl) Crystals for Gamma Rays from Thick Disk Sources.
GAMMOMAbstractC00135 ALLMF 00Gamma-Ray Moments Method Codes--GRMM and SPENCER.
GAMMOM-IAbstractC00226 I0360 00Gamma-Ray Moments Method Code System.
GAMMONAbstractD00071 ALLCP 00Activation Library for Fusion Reaction Application and Other Design Studies.
GAMTABAbstractD00032 I0360 00Radioactive-Decay Gamma-Rays Ordered by Energy and Nuclide.
GAMTOT78AbstractD00109 CY00I 00Compilation of Radioactive Decay and Capture Gamma Rays.
GAMX1AbstractP00209 I0370 00A Computer Code System for Evaluating Spectra Peak Areas.
GANAPOL-ABNTTAbstractM00011 MNYCP 00Analytical Benchmarks for Nuclear Engineering Applications: Case Studies in Neutron Transport Theory.
GANDR/SEMOVEAbstractC00765 PCX86 00Program for Calculating Derivatives of Processed Multigroup Nuclear Data by Discrete Differences.
GAPCON-THERMALAbstractP00499 C7600 00Code System to Calculate Fuel Steady State & Transient Behavior.
GARGAbstractD00073 C0000 0027-Group Neutron Cross Sections in Discrete Ordinates Format Generated with FIGERO (PSR-149) from ENDF-B Data.
GARLIBAbstractD00013 I3565 01Multigroup Resonance-Region Cross Sections for Use in Shielding Calculations.
GARLIBAbstractD00013 I7090 00Multigroup Resonance-Region Cross Sections for Use in Shielding Calculations.
GAROLAbstractP00033 I7090 00Calculation of Resonance Neutron Absorption in Two-Region Problems.
GASPARAbstractC00463 I3033 01Calculates Radiation Exposure to Man from Routine Air Releases of Nuclear Reactor Effluents.
GASPAR IIAbstractC00463 D0780 00Calculates Radiation Exposure to Man from Routine Air Releases of Nuclear Reactor Effluents.
GASSAbstractC00080 I7090 00Monte Carlo Calculation of Self Shielding by Encapsulated Gamma-Ray Sources.
GAUSS VAbstractP00045 I0360 00A Code system for Analysis of Gamma-Ray Spectra from Ge(Li) Spectrometers.
GAUSS VIIAbstractP00045 C0000 00A Code system for Analysis of Gamma-Ray Spectra from Ge(Li) Spectrometers.
GBANISNAbstractC00628 IRISC 00One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering with the GroupBand Option.
GCIAbstractP00421 IBMPC 00Generic Communications Index
GEAF-1AbstractD00158 D8810 00100 Group Cross Sections for Neutron Activation.
GECINXAbstractP00193 H6000 00A Code System for Collapsing Multigroup Cross Sections in CCCC Format.
GEFAbstractP00564 PCX86 02A GEneral description of the Fission process.
GELI2/SPAN2AbstractP00094 I0360 00Calculation of Nuclide Abundaces from Multichannel Gamma-ray Spectra.
GEMAbstractP00540 PC586 00Monte-Carlo Code for Simulating a Decaying Process of an Excited Nucleus.
GENII 2.10AbstractC00737 PCX86 02Environmental Radiation Dosimetry Software System.
GENII-LIN 2.1AbstractC00728 PC586 01GENII-LIN Multipurpose Health Physics Code System with a New Object-Oriented Interface, Release 2.0.
GENP-2AbstractC00575 ALLMF 00Generalized Perturbation Theory Code System.
GENRDAbstractP00040 C6600 00Free Format Card Input Processor.
GENRDAbstractP00040 I0360 00Free Format Card Input Processor.
GERESAbstractP00241 I0370 00A Code to Produce Cross-Section Libraries for ANISN Based on Heterogeneous Fast Reactor Cell Calculations Using MC2II Data.
GES_MCAbstractC00742 PC586 00Gamma-electron Efficiency Simulator, Version 3.1
GETOUTAbstractC00461 C0176 00A Computer Code System for Predicting One-Dimensional Radionuclide Decay Chain Transport through Geologic Media.
GFX-GAMIXAbstractC00397 I3033 00A Spherical Harmonics Code System for Evaluation of Terrestrial Gamma-Radiation Fields.
GGC-3AbstractP00012 I3565 00Multigroup Cross Section Code System for Use in Diffusion and Transport Codes.
GGC-3 & GGC-4AbstractP00012 I3675 00Multigroup Cross Section Code System for Use in Diffusion and Transport Codes.
GGC-4AbstractP00012 U1108 00Multigroup Cross Section Code System for Use in Diffusion and Transport Codes.
GGG-GPAbstractC00564 IBMPC 00Kernel Integration Code System - Multigroup Gamma-Ray Scattering Using the GP Buildup Factor.
GGTC-ENELAbstractP00128 I0360 00Code System for Producing Few-Group Neutron Cross Sections from Multigroup Data Libraries.
GICX40AbstractD00092 ALLCP 00Coupled 42-Neutron, 21-Gamma-Ray Group Cross Sections for 40 Elements in Group Independent Form for Fusion Reactor Calculations.
GIFTAbstractP00124 C0076 00A Combinatorial Geometry Code System with Model Testing Routines.
GIFTAbstractP00124 D0VAX 00A Combinatorial Geometry Code System with Model Testing Routines.
GIFTAbstractP00124 U0000 00A Combinatorial Geometry Code System with Model Testing Routines.
GIPAbstractP00229 IBMPC 00Group-Organized Cross-Section Input Program.
GIRAFFEAbstractP00304 I3033 00General Isotope Release Analysis For Failed Elements.
GLUCSAbstractP00192 D0VAX 00A Generalized Least-Squares Code System for Updating Cross Section Evaluations with Correlated Data Sets.
GMAAbstractP00367 MNYCP 00Code System for Calculation of Reactor Accident Consequences.
GNASH-FKKAbstractP00535 MNYCP 00Pre-equilibrium, Statistical Nuclear-Model Code System for Calculation Cross Sections and Emission Spectra, Version gn9cp8.
GNOMERAbstractC00625 MNYCP 01Multigroup 3-Dimensional Neutron Diffusion Nodal Code System with Thermohydraulic Feedbacks.
GOFRRAbstractP00127 I0360 00Generator of Graphical Output of DOT and ANISN Fluxes and Reaction Rates.
GRACE-IIAbstractC00026 I3675 00Gamma Ray Kernel Integration Dose Rate and Heating Code-Cylinders and Spheres.
GRASS-SSTAbstractP00489 MNYCP 00Code System to Predict Fission-Gas Release & Fuel Swelling.
GREAT-GRASSAbstractC00143 I3675 00Monte Carlo Radiation Transport Code Systems for Fallout Shielding.
GRENADEAbstractC00516 C1787 00Green's Function Nodal Algorithm for the Diffusion Equation.
GRENADEAbstractC00516 D0780 00Green's Function Nodal Algorithm for the Diffusion Equation.
GRESS 3.0AbstractP00231 MFMWS 02Gradient Enhanced Software System.
GRETELAbstractP00100 I0370 00Analyzer and Processor of Ge(Li) Gamma-Ray Spectrometric Data.
GRFPAKAbstractP00478 I0360 00Code System to Plot CORTES FEM Results.
GROUP STRUCTUREAbstractD00156 ALLCP 00Standard Energy Group Structures Of Cross Section Libraries For Reactor Shielding, Reactor Cell Fusion Neutronics Applications: VITAMIN-J, ECC0-33, ECC0-2000.
GROUPXSAbstractP00246 C0740 00Processing of Double-Differential Cross Sections in the New ENDF-VI Format.
GRPANLAbstractP00321 D0VAX 00Code System for Analyzing Ge and Alpha-Particle Detector Spectra.
GRSACAbstractC00774 PCX86 00Graphite Reactor Severe Accident Code.
GRTUNCL3DAbstractC00721 MNYCP 01Code to Calculate Semi-Analytic First Collision Source and Uncollided Flux.
GT2R2AbstractP00483 ALLMF 00Code System to Calculate Fuel Rod Thermal Performance.
GUI2QAD-3DAbstractC00697 PC586 01Point Kernel Code System for Neutron and Gamma-Ray Shielding Calculations in Complex Geometry, Including a Graphical User Interface.
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.