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| Packages starting with G |
| Package Name | Abstract | RSICC Tapelist | Title |
| G3-6ED | Abstract | C00075 C6600 00 | Kernel Integration Code System - Multigroup Gamma Ray Scattering. |
| G3-6ED | Abstract | C00075 I3033 00 | Kernel Integration Code System - Multigroup Gamma Ray Scattering. |
| GABAS | Abstract | P00175 U1108 00 | A Code System for Generating Composite Time-Dependent Fission Produce Spectra. |
| GADJET | Abstract | C00115 C6600 00 | Monte Carlo Gamma-Ray Adjoint Energy Transport Code in Complex Three-Dimensional Geometry. |
| GADRAS-DRF-19.4.0 | Abstract | P00610 PCX86 06 | Gamma Detector Response and Analysis Software–Detector Response Function. |
| GAINCALB | Abstract | P00056 I0360 00 | Determination of the Gain Used with Organic Scintillation Detect. |
| GAKER-KIRA | Abstract | C00813 C3600 00 | Energy Transfer of Protons in H2O or Polyethylene and Deuterons in D2O. |
| GALAXY-6 | Abstract | P00098 I0370 00 | Neutron Multigroup Cross Section Processor. |
| GALE BWR | Abstract | C00335 U1100 00 | Boiling Water and Pressurized Water Reactors Gaseous and Liquid Effluents Radiological Assessment Code System. |
| GALE PWR & BWR | Abstract | C00335 I3033 00 | Boiling Water and Pressurized Water Reactors Gaseous and Liquid Effluents Radiological Assessment Code System. |
| GALE86 | Abstract | C00506 MNYCP 02 | Calculation of Routine Radioactive Releases in Gaseous and Liquid Effluents from Boiling Water and Pressurized Water Reactors. |
| GAMAN | Abstract | P00083 DP010 00 | Qualitative and Quantitative Evaluation of Ge(Li) Gamma-Ray Spectra. |
| GAMANAL | Abstract | P00506 D0VAX 00 | Code System for Computerized Quantitative Analysis By Gamma-Ray Spectrometry. |
| GAMDAT-78 | Abstract | D00083 I0370 00 | Library of Gamma-Ray Decay Data for 2055 Radionuclides. |
| GAMIDENT | Abstract | P00154 C0000 00 | A Program to Aid in the Identification of Unknown Materials by Gamma-ray Spectroscopy. |
| GAMLEG-75 | Abstract | P00086 C7600 00 | Multigroup Cross Section Generator for Photon Transport Calculations. |
| GAMLIB | Abstract | D00006 I0360 00 | 99-Group Neutron Cross Sections for Use in the GAM Portion of the GGC Multigroup Cross Section Code. |
| GAMMA | Abstract | P00095 I0360 00 | Monte Carlo Code System for Calculating Efficiencies and Response Functions of NaI(Tl) Crystals for Gamma Rays from Thick Disk Sources. |
| GAMMOM | Abstract | C00135 ALLMF 00 | Gamma-Ray Moments Method Code System. |
| GAMMOM-I | Abstract | C00226 I0360 00 | Gamma-Ray Moments Method Code System. |
| GAMMON | Abstract | D00071 ALLCP 00 | Gamma-Ray Moments Method Code System. |
| GAMTAB | Abstract | D00032 I0360 00 | Radioactive-Decay Gamma-Rays Ordered by Energy and Nuclide. |
| GAMTOT78 | Abstract | D00109 CY00I 00 | Compilation of Radioactive Decay and Capture Gamma Rays. |
| GAMX1 | Abstract | P00209 I0370 00 | A Computer Code System for Evaluating Spectra Peak Areas. |
| GANAPOL-ABNTT | Abstract | M00011 MNYCP 00 | Analytical Benchmarks; Case Studies in Neutron Transport Theory. |
| GANDR/SEMOVE | Abstract | C00765 PCX86 00 | Program for Calculating Derivatives of Processed Multigroup Nuclear Data by Discrete Differences. |
| GAPCON-THERMAL | Abstract | P00499 C7600 00 | Code System to Calculate Fuel Steady State & Transient Behavior. |
| GARG | Abstract | D00073 C0000 00 | 27-Group Neutron Cross Sections in Discrete Ordinates Format Generated with FIGERO (PSR-149) from ENDF-B Data. |
| GARLIB | Abstract | D00013 I3565 01 | Multigroup Resonance-Region Cross Sections for Use in Shielding Calculations. |
| GARLIB | Abstract | D00013 I7090 00 | Multigroup Resonance-Region Cross Sections for Use in Shielding Calculations. |
| GAROL | Abstract | P00033 I7090 00 | Calculation of Resonance Neutron Absorption in Two-Region Problems. |
| GASPAR | Abstract | C00463 I3033 01 | Calculates Radiation Exposure to Man from Routine Air Releases of Nuclear Reactor Effluents. |
| GASPAR II | Abstract | C00463 D0780 00 | Calculates Radiation Exposure to Man from Routine Air Releases of Nuclear Reactor Effluents. |
| GASS | Abstract | C00080 I7090 00 | Monte Carlo Calculation of Self Shielding by Encapsulated Gamma-Ray Sources. |
| GAUSS V | Abstract | P00045 I0360 00 | A Code system for Analysis of Gamma-Ray Spectra from Ge(Li) Spectrometers. |
| GAUSS VII | Abstract | P00045 C0000 00 | A Code system for Analysis of Gamma-Ray Spectra from Ge(Li) Spectrometers. |
| GBANISN | Abstract | C00628 IRISC 00 | One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering with the GroupBand Option. |
| GCI | Abstract | P00421 IBMPC 00 | Generic Communications Index |
| GEAF-1 | Abstract | D00158 D8810 00 | 100 Group Cross Sections for Neutron Activation. |
| GECINX | Abstract | P00193 H6000 00 | A Code System for Collapsing Multigroup Cross Sections in CCCC Format. |
| GEF | Abstract | P00564 PCX86 03 | A GEneral description of the Fission process. |
| GELI2/SPAN2 | Abstract | P00094 I0360 00 | Calculation of Nuclide Abundaces from Multichannel Gamma-ray Spectra. |
| GEM | Abstract | P00540 PC586 00 | Monte-Carlo Code for Simulating a Decaying Process of an Excited Nucleus. |
| GENII 2.10 | Abstract | C00737 PCX86 02 | Environmental Radiation Dosimetry Software System. |
| GENII-LIN 2.1 | Abstract | C00728 PC586 01 | GENII-LIN Multipurpose Health Physics Code System with a New Object-Oriented Interface, Release 2.0. |
| GENP-2 | Abstract | C00575 ALLMF 00 | Generalized Perturbation Theory Code System. |
| GENRD | Abstract | P00040 C6600 00 | Free Format Card Input Processor. |
| GENRD | Abstract | P00040 I0360 00 | Free Format Card Input Processor. |
| GERES | Abstract | P00241 I0370 00 | A Code to Produce Cross-Section Libraries for ANISN Based on Heterogeneous Fast Reactor Cell Calculations Using MC2II Data. |
| GES_MC | Abstract | C00742 PC586 00 | Gamma-electron Efficiency Simulator. |
| GETOUT | Abstract | C00461 C0176 00 | A Computer Code System for Predicting One-Dimensional Radionuclide Decay Chain Transport through Geologic Media. |
| GFX-GAMIX | Abstract | C00397 I3033 00 | A Spherical Harmonics Code System for Evaluation of Terrestrial Gamma-Radiation Fields. |
| GGC-3 | Abstract | P00012 I3565 00 | Multigroup Cross Section Code System for Use in Diffusion and Transport Codes. |
| GGC-3 & GGC-4 | Abstract | P00012 I3675 00 | Multigroup Cross Section Code System for Use in Diffusion and Transport Codes. |
| GGC-4 | Abstract | P00012 U1108 00 | Multigroup Cross Section Code System for Use in Diffusion and Transport Codes. |
| GGG-GP | Abstract | C00564 IBMPC 00 | Kernel Integration Code System - Multigroup Gamma-Ray Scattering Using the GP Buildup Factor. |
| GGTC-ENEL | Abstract | P00128 I0360 00 | Code System for Producing Few-Group Neutron Cross Sections from Multigroup Data Libraries. |
| GICX40 | Abstract | D00092 ALLCP 00 | Coupled 42-Neutron, 21-Gamma-Ray Group Cross Sections for 40 Elements in Group Independent Form for Fusion Reactor Calculations. |
| GIFT | Abstract | P00124 C0076 00 | A Combinatorial Geometry Code System with Model Testing Routines. |
| GIFT | Abstract | P00124 D0VAX 00 | A Combinatorial Geometry Code System with Model Testing Routines. |
| GIFT | Abstract | P00124 U0000 00 | A Combinatorial Geometry Code System with Model Testing Routines. |
| GIP | Abstract | P00229 IBMPC 00 | Group-Organized Cross-Section Input Program. |
| GIRAFFE | Abstract | P00304 I3033 00 | General Isotope Release Analysis For Failed Elements. |
| GLUCS | Abstract | P00192 D0VAX 00 | A Generalized Least-Squares Code System for Updating Cross Section Evaluations with Correlated Data Sets. |
| GMA | Abstract | P00367 MNYCP 00 | Code System for Calculation of Reactor Accident Consequences. |
| GNASH-FKK | Abstract | P00535 MNYCP 00 | Pre-equilibrium, Statistical Nuclear-Model Code System for Calculation Cross Sections and Emission Spectra. |
| GNOMER | Abstract | C00625 MNYCP 01 | Multigroup 3-Dimensional Neutron Diffusion Nodal Code System with Thermohydraulic Feedbacks. |
| GOFRR | Abstract | P00127 I0360 00 | Generator of Graphical Output of DOT and ANISN Fluxes and Reaction Rates. |
| GRACE-II | Abstract | C00026 I3675 00 | Gamma Ray Kernel Integration Dose Rate and Heating Code-Cylinders and Spheres. |
| GRASS-SST | Abstract | P00489 MNYCP 00 | Code System to Predict Fission-Gas Release & Fuel Swelling. |
| GREAT-GRASS | Abstract | C00143 I3675 00 | Monte Carlo Radiation Transport Code Systems for Fallout Shielding. |
| GRENADE | Abstract | C00516 C1787 00 | Green's Function Nodal Algorithm for the Diffusion Equation. |
| GRENADE | Abstract | C00516 D0780 00 | Green's Function Nodal Algorithm for the Diffusion Equation. |
| GRESS 3.0 | Abstract | P00231 MFMWS 02 | Gradient Enhanced Software System. |
| GRETEL | Abstract | P00100 I0370 00 | Analyzer and Processor of Ge(Li) Gamma-Ray Spectrometric Data. |
| GRFPAK | Abstract | P00478 I0360 00 | Code System to Plot CORTES FEM Results. |
| GROUP STRUCTURE | Abstract | D00156 ALLCP 00 | Standard Energy Group Structures Of Cross Section Libraries For Reactor Shielding, Reactor Cell Fusion Neutronics Applications: VITAMIN-J, ECC0-33, ECC0-2000. |
| GROUPSTRUCTURES | Abstract | D00274 MNYCP 00 | GROUPSTRUCTURES, VITAMIN-J, XMAS, ECCO-33, ECCO2000 Standard Group Structures |
| GROUPXS | Abstract | P00246 C0740 00 | Processing of Double-Differential Cross Sections in the New ENDF-VI Format. |
| GRPANL | Abstract | P00321 D0VAX 00 | Code System for Analyzing Ge and Alpha-Particle Detector Spectra. |
| GRSAC | Abstract | C00774 PCX86 00 | Graphite Reactor Severe Accident Code. |
| GRTUNCL3D | Abstract | C00721 MNYCP 01 | Code to Calculate Semi-Analytic First Collision Source and Uncollided Flux. |
| GRUCON | Abstract | P00615 MNYCP 00 | Data Processing for Evaluated Working libraries (transport and shielding) |
| GT2R2 | Abstract | P00483 ALLMF 00 | Code System to Calculate Fuel Rod Thermal Performance. |
| GUI2QAD-3D | Abstract | C00697 PC586 01 | A Graphical User Interface for QAD-CGPIC, a Point Kernal Code for Neutron and Gamma-Ray Shielding Calculations in Complex Geometry. |