Online Catalog
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Packages with Keyword: ONE-DIMENSION
Package NameAbstractRSICC TapelistTitle
1DB-2DB-3DBAbstractC00741 PC586 00One-Dimensional Diffusion Code System for Nuclear Reactor.
ADOAbstractC00189 I3675 00Aerojet Discrete Ordinates Calculational System.
AIRDIFAbstractC00360 C6600 00A Two-Dimensional Atmospheric Radiation Diffusion Code.
ANISN-ORNLAbstractC00254 MNYCP 02One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering.
ANISN-PCAbstractC00514 IBMPC 00Multigroup One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering.
APARNA-IIAbstractC00296 I0360 00Integral Transport Theory Code System Based on Discrete Ordinate Representation in Space and Direction-Slab Geometry.
ARMYL-GAbstractC00297 U1106 00Calculation of Transmission Factors for Gamma Rays from Nuclear Explosions.
ARMYL-NAbstractC00298 U1106 00Calculation of Transmission Factors for Neutrons from Nuclear Explosions.
ASFIT-VARIAbstractC00336 H0000 00Gamma-Ray Transport Code System for One-Dimensional Finite Systems.
ASFIT-VARIAbstractC00336 IBMPC 00Gamma-Ray Transport Code System for One-Dimensional Finite Systems.
ASOPAbstractC00126 IRISC 00Multigroup One-Dimensional Discrete Ordinates Transport Code System for Shield Optimization.
AT123DAbstractC00417 I0360 00Analytical Transient One-, Two-, and Three-Dimensional Simulation of Waste Transport in an Aquifer System.
BERMUDAAbstractC00616 FV260 03Discrete Ordinates Code System for Shielding Analysis for Use with Fusion and Fission Reactors.
BIGGIAbstractC00066 I3675 00Numerical Gamma-Ray Transport Code for Plane or Spherical Multilayer Geometry.
BIGGIAbstractC00066 U1108 00Numerical Gamma-Ray Transport Code for Plane or Spherical Multilayer Geometry.
BISON 1.5AbstractC00464 HM200 00One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System.
BISON-CAbstractC00659 MNYWS 00One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System.
CAFDATSAbstractP00549 MNYCP 00Converter of Angular Fluxes of DORT, ANISN and TORT Systems.
CASCADEAbstractC00176 C6600 00Monte Carlo Simulation of the Transport of High Energy Electrons and Photons in Matter.
CASCADEAbstractC00176 I0360 00Monte Carlo Simulation of the Transport of High Energy Electrons and Photons in Matter.
CEPXS/ONELD 1.0AbstractC00544 MNYCP 02One-Dimensional Coupled Electron-Photon Multigroup Discrete Ordinates Code System.
DANTSYS 3.0AbstractC00547 MFMWS 01One-, Two-, and Three-Dimensional, Multigroup, Discrete-Ordinates Transport Code System.
DASH-FPAbstractC00366 C0000 00A One-Dimensional Analytic-Numerical Solution to the Problem of Multicomponent Time-Dependent Diffusion of Fission Products.
DAVEAbstractC00166 I3675 00Monte Carlo Gamma-Ray Transport Code System in One-Dimensional Spherical Geometry.
DDXCODESAbstractC00583 FM380 00One-, Two- and Three-Dimensional Transport Codes Using Multigroup Double-Differential Form Cross Sections.
DKRAbstractC00323 CY000 00A Radioactivity and Dose Rate Calculation Code System for Fusion Reactors.
DOORS 3.2AAbstractC00650 MFMWS 04One, Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System.
DOPEX-1D2CAbstractC00214 I0360 00A One-Dimensional, Two-Constraint Radiation Shield Optimization Code System.
DTF-69AbstractC00130 C6600 00Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering.
DTF-INDIAAbstractC00458 I0370 00Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering.
DTF-IVAbstractC00042 C6600 00Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering.
DTF-IV MODIFIEDAbstractC00042 I0370 00Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering.
DTF-TRACAAbstractC00412 U1100 00Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering.
DTKAbstractC00223 I3675 00One-Dimensional Multigroup Neutron Transport Code System.
DUST-BNLAbstractC00634 PC386 00Disposal Unit Source Term by One-Dimensional, Transient, Finite-Difference, Subsurface Release and Transport of Contaminants.
EDMULT 6.4AbstractC00430 MNYCP 02Evaluates Electron Depth-Dose Distributions in Multilayer Slab Absorbers.
ELTRANAbstractC00155 C3600 00One-Dimensional Monte Carlo Electron Transport Code System.
ENEDEPAbstractC00227 GE400 00Energy Deposition Code System for GE 265 Time-Sharing System.
FDKRAbstractC00541 I4381 00Radioactivity and Dose Rate Calculation Code for Fission, Fusion and Hybrid Reactors.
FIPDIGAbstractC00251 I0360 00One-Dimensional Time-Dependent Fission Product Diffusion Code System.
FPZDAbstractC00603 PC386 00Code System for Multigroup Neutron Diffusion/Depletion Calculations.
FSCATTAbstractC00186 I3033 00Discrete Ordinates Gamma-Ray Transport Code System in Plane Geometry.
FSCATTAbstractC00186 U1108 00Discrete Ordinates Gamma-Ray Transport Code System in Plane Geometry.
GAMMOMAbstractC00135 ALLMF 00Gamma-Ray Moments Method Code System.
GAMMOM-IAbstractC00226 I0360 00Gamma-Ray Moments Method Code System.
GBANISNAbstractC00628 IRISC 00One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering with the GroupBand Option.
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.
INDRAAbstractC00303 I0360 00A Modular System for Calculating the Neutronics and Photonics Characteristics of a Fusion Reactor Blanket.
ITS6
FEDC
AbstractC00792 PCX86 00Integrated TIGER Series of Coupled Electron/Photon Monte Carlo Transport Codes System.
JN-METD 2&1AbstractC00208 I0370 00Neutron Transport Code System with Isotropic Scattering, Bare Slabs and Homogeneous Slabs (JN Method 1), Multilayer Slabs (JN Method 2).
LASERAbstractC00344 I0360 00A One-Dimensional, Neutron-Thermalization, Lattice-Cell Program Based on MUFT and THERMOS.
MEDUSA-PIJAbstractC00349 F2307 00One-Dimensional Lagrangian Code for Plasma Hydrodynamic Analysis of a Fusion Pellet Driven by Ion Beams.
MORSE-LAbstractC00261 C6600 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MTR_PC 2.6AbstractC00674 PC386 00Modular Code System for Neutronics, Thermalhydraulics and Shielding Calculations.
MUSPALBAbstractC00171 ICL00 00Albedo Calculation of Multigroup Spectra of Neutrons Transmitted Through Multilayer Slab Shielding.
NAPAbstractC00101 I7090 00Multigroup Time-Dependent Neutron Activation Prediction Code.
NITRANAbstractC00582 FM380 00Neutron Transport Code System Based On Anisotropic Scattering.
NRNAbstractC00054 C6600 00Multigroup Removal-Diffusion Code System for Planes, Cylinders and Spheres.
OGRE-MINAbstractC00409 DGECL 00A General-Purpose Monte Carlo Gamma-Ray Transport Code System for Minicomputers.
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.
ORPHEE VIAbstractC00159 I3675 00Kernel Integration Code System - Attenuation of Fast Neutrons in Cylindrical Layers of Water and Dense Material.
PADLOCAbstractC00330 U0000 00A One-Dimensional, Time-Dependent Program for Calculating Coolant and Plateout Fission Product Concentrations in a Network of Pipes.
PALLAS-1D(VII)AbstractC00380 FM380 00Multigroup Time-Independent Neutron Transport Code System for Plane or Spherical Geometry.
PIGGAbstractC00138 C3600 00A Multigroup One-Dimensional P-1 Radiation Transport Code System.
PIPEAbstractC00219 I0360 00Numerical Gamma-Ray Transport Code System for Plane/Spherical Geometry.
PNAbstractC00818 I0370 00MultiGroup Neutron Transport.
PROBAbstractC00287 I0370 00Multigroup One-Dimensional Transport Code System, Collision Probability Method.
RADHEAT-V4AbstractC00300 FM380 00A Code System To Generate Multigroup Constants and Analyze Radiation Transport for Shielding Safety Evaluation.
REDIFFUSIONAbstractC00347 I0360 00One-Dimensional Neutron Removal-Diffusion and Gamma-Ray Kernel Integration or Diffusion Theory Calculator.
SABINE-3AbstractC00121 C7600 00Spinney (Removal-Diffusion) Shielding Code System in One-Dimensional Geometry.
SABINE-3AbstractC00121 I0370 00Spinney (Removal-Diffusion) Shielding Code System in One-Dimensional Geometry.
SABINE-3AbstractC00121 U1106 00Spinney (Removal-Diffusion) Shielding Code System in One-Dimensional Geometry.
SABINE-PCAbstractC00121 IBMPC 00Spinney (Removal-Diffusion) Shielding Code System in One-Dimensional Geometry.
SAMSYAbstractC00315 C0073 00A One-Dimensional Multilayer Multigroup Neutron Removal-Diffusion and Gamma-Ray Point Kernel Calculator.
SEDONEAbstractC00345 I0360 00A Simulator of Tidal Transient Hydrodynamic Sediment Concentrations Conditions in Controlled Rivers and Estuaries.
SENSITAbstractC00405 C7600 00One-Dimensional, Multigroup Cross Section and Design Sensitivity and Uncertainty Analysis Code System - Generalized Perturbation Theory.
SHADOKAbstractC00216 C6600 00Transport Code Systems, P1 Scattering in Infinite Cylindrical and Spherical Geometries by Polynomial Approximation.
SLDNAbstractC00221 A1000 00Code System for Shielding Calculations by the Method of Invariant Imbedding.
SLDNAbstractC00221 F2307 00Code System for Shielding Calculations by the Method of Invariant Imbedding.
SLDNAbstractC00221 FM200 00Code System for Shielding Calculations by the Method of Invariant Imbedding.
SLDNAbstractC00221 GE625 00Code System for Shielding Calculations by the Method of Invariant Imbedding.
SLDNAbstractC00221 I0360 00Code System for Shielding Calculations by the Method of Invariant Imbedding.
SNAP-3DAbstractC00434 MNYCP 01Multigroup Complex Geometry Neutron Diffusion Code System.
SNEXAbstractC00353 C0000 00A One-Dimensional Single Group Discrete Ordinates Transport Code System.
STRAINTAbstractC00259 I0360 00One-Dimensional Multigroup Neutron Transport Discrete Ordinates Code System.
SWANAbstractC00248 C0000 00Code System for Analysis and Optimization of Fusion Reactor Nucleonic Characteristics.
SWANAbstractC00248 CY000 00Code System for Analysis and Optimization of Fusion Reactor Nucleonic Characteristics.
SWANAbstractC00248 I0360 00Code System for Analysis and Optimization of Fusion Reactor Nucleonic Characteristics.
SWANLAKEAbstractC00204 C6600 00Cross Section Sensitivity Analysis Code System for One-Dimensional Discrete Ordinates Calculations.
SWANLAKEAbstractC00204 I3033 00Cross Section Sensitivity Analysis Code System for One-Dimensional Discrete Ordinates Calculations.
SWAP-9AbstractC00788 C0740 001-D Stress Analysis for Hydrostatic and Elastic Plastic Materials.
TASKAbstractC00184 I0360 00Generalized One-Dimensional Radiation Transport and Diffusion Kinetics Code System.
TDAAbstractC00180 MNYWS 01A Time-Dependent, Multigroup, One-Dimensional, Discrete Ordinates Transport Code System.
TDTAbstractC00256 I0360 00Generalized One-Dimensional Multigroup Time-Dependent Transport and Diffusion Kinetic Code System.
TESSAbstractC00215 C3600 00Multigroup Discrete Ordinates Code System for Slab and Spherical Geometries.
THIDA-2AbstractC00410 FM380 00Code System for the Calculation of Transmutation, Activation, Decay Heat and Dose Rate in Fusion Reactors.
TIMEXAbstractC00274 C7600 00One Dimensional, Time Dependent Multigroup Explicit Discrete Ordinates Radiation Transport Code System with Anisotropic Scattering.
TIMEXAbstractC00274 CY000 00One Dimensional, Time Dependent Multigroup Explicit Discrete Ordinates Radiation Transport Code System with Anisotropic Scattering.
TIMEXAbstractC00274 U1106 00One Dimensional, Time Dependent Multigroup Explicit Discrete Ordinates Radiation Transport Code System with Anisotropic Scattering.
TMMSAbstractC00246 I0360 00Gamma-Ray Penetration Shielding Code System, Transmission Matrix Method.
TPHEXAbstractC00421 C0173 00Transmission Probability Code System for Calculating Neutron Flux Distributions in Hexagonal Geometry.
TPHEXAbstractC00421 CYXMP 00Transmission Probability Code System for Calculating Neutron Flux Distributions in Hexagonal Geometry.
UNIMUG3AbstractC00407 C0170 00Solves Multigroup Diffusion Equations in One-Dimensional Systems.
USRHYDAbstractC00197 I3675 00Electron and X-Ray Energy Deposition and Hydrodynamics Code System.
XSDRNAbstractC00123 C0073 00Multigroup One-Dimensional Discrete Ordinates Spectral Averaging N Transport Code System.
XSDRNAbstractC00123 I0360 00Multigroup One-Dimensional Discrete Ordinates Spectral Averaging N Transport Code System.
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.