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
USSO -- US Distribution Only
USUNV -- US Universities Only
Packages starting with D
Package NameAbstractRSICC TapelistTitle
D2OAbstractP00398 PC486 00Code System for Computing Thermodynamic and Transport Properties of D2O.
DABL69AbstractD00130 I0360 01Defense Nuclear Applications Broad-Group Library based on ENDF/B-V in ANISN Format.
DACRINAbstractC00273 U1100 00Airborne Radionuclide Organ Dose Calculational System.
DANCOFF3AbstractP00279 D8810 00Calculates Dancoff Correction.
DANCOFF-MCAbstractP00509 MNYCP 00Code System for Monte Carlo Calculation of Dancoff Factors in Irregular Geometries.
DANESS V1.0
FEDC
AbstractP00555 MNYCP 00Dynamic Analysis of Nuclear Energy System Strategies.
DANTEAbstractP00185 I0370 00Unfolding Code System for Energy Spectra Evaluation for Dosimetry Purposes.
DASH-FPAbstractC00366 C0000 00A One-Dimensional Analytic-Numerical Solution to the Problem of Multicomponent Time-Dependent Diffusion of Fission Products.
DASQHEAbstractP00278 D8810 00Calculates Dancoff Corrections Factors.
DATINITAbstractP00258 DGMV1 00Interactive Program To Access Photon Interaction Data.
DAVEAbstractC00166 I3675 00Monte Carlo Gamma-Ray Transport Code System in One-Dimensional Spherical Geometry.
DCHAIN 1.3AbstractC00640 MNYCP 01Code System for Radioactive Decay and Reaction Chain Calculations.
DCHAIN2AbstractC00370 PC486 00A Code System for Calculation of Transmutation of Nuclides.
DCHAIN-SP2001AbstractC00712 MNYWS 01Code System for Analyzing Decay and Build-up Characteristics of Spallation Products.
DCTDOSAbstractC00520 IBMPC 00Neutron and Gamma-Ray Penetration in Composite Duct Systems.
DDXCODESAbstractC00583 FM380 00One-, Two- and Three-Dimensional Transport Codes Using Multigroup Double-Differential Form Cross Sections.
DDXLIBAbstractD00123 FM380 01125-Neutron Group Double Differential Cross Section Library.
DECAYREMAbstractD00030 I0360 02Radioactive Decay Spectra in EXREM Format.
DECDC 1.0AbstractD00213 MNYCP 00Nucear Decay Data Files for Radiation Dosimetry Calculations.
DEISAbstractC00455 C6600 00Draft Environmental Impact Statement on Licensing Requirements for Land Disposal of Radioactive Waste.
DEMON & DEMON RAbstractC00181 I3675 00Demonstration Monte Carlo Code System in Slab Geometry.
DENISAbstractP00082 I0360 00Monte Carlo Simulation of the Capture and Detection of Neutrons with Large Liquid Scintillators.
DEPLETORAbstractP00523 MNYCP 00Code System to Provide Depletion Capability to the U.S. NRC PARCS Code
DEPOSITION
FEDC
AbstractP00420 IBMPC 00Code System to Calculate Particle Penetration Through Aerosol Transport Lines.
DETAN 95AbstractP00361 MNYCP 00Code System to Calculate Spectrum-Averaged Cross Sections and Detector Responses in Neutron Spectra.
DIAMANT2AbstractC00414 PC386 00Multigroup Two-Dimensional Discrete Ordinates Transport Code System for Triangular Geometry, Release 2.0.
DIF3D 11.0
FEDC
AbstractC00784 MNYCP 01Code System Using Variational Nodal Methods and Finite Difference Methods to Solve Neutron Diffusion and Transport Theory Problems.
DIFBASAbstractP00334 MNYCP 00A Bayesian Approach to Unfolding a Neutron Spectrum from a Spectrum of Recoiled Protons.
DIFMODAbstractC00572 I3083 00A Computer Program To Calculate The Leaching of Radionuclides and the Corrosion of Cemented Waste Forms in Water or Brine.
DIMENAbstractP00341 IBMPC 00Code System for Isotope Identification by Gamma-Ray Analysis.
DINTAbstractP00049 C6600 00Multigroup Coherent-Incoherent Cross Section Data Generator for Photon Transport Calculations.
DINTAbstractP00049 I0360 00Multigroup Coherent-Incoherent Cross Section Data Generator for Photon Transport Calculations.
DINT-YAECAbstractC00306 ALLMF 00Evaluator of I1 and I2 Integrals as Used in Long-Term External Gamma-Ray Doses from Routine Atmospheric Releases.
DIPHOAbstractC00140 I3675 00Monte Carlo Gamma-Ray Code System-Infinite Medium, Mono-energetic and Isotropic Point Source.
DISDOSAbstractC00170 I0360 00Calculation of Dose Distribution in Human Phantoms Irradiated by External Photon Sources.
DISKTRANAbstractC00533 CYXMP 00Dose Calculations at Detectors from the End of a Cylinder Using DOT IV Scalar Flux Data.
DISKTRANAbstractC00533 I3033 00Dose Calculations at Detectors from the End of a Cylinder Using DOT IV Scalar Flux Data.
DISPERSAbstractC00454 MNYCP 00Mathematical Models for Dispersion of Radionuclides
DIXY-2AbstractC00812 I0370 002-D Homogeneous and Inhomogeneous Neutron Diffusion N X-Z, R-Z, R-Theta Geometry with Perturbation.
DKRAbstractC00323 CY000 00A Radioactivity and Dose Rate Calculation Code System for Fusion Reactors.
DLSAbstractC00264 C6600 00Two-Dimensional Shielding Calculational System with Diffusion Theory and Line-of-Sight Method.
DOMINOAbstractP00064 I0360 00A General Purpose Code System for Coupling Discrete Ordinates and Monte Carlo Radiation Transport Calculations.
DOMINO-IIAbstractP00162 I3033 00General Purpose Code System for Coupling DOT-IV Discrete Ordinates and Monte Carlo Radiation Transport Calculations.
DOMUSAbstractP00301 IPCXT 00A Program for Decomposing A Two-Dimensional Spectrum.
DOORS 3.2AAbstractC00650 MFMWS 04One, Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System.
DOPEXAbstractC00177 I3675 00Laminated Shield Weight Optimization Code System-Steepest Descent Calculational Model.
DOPEXAbstractC00177 U1108 00Laminated Shield Weight Optimization Code System-Steepest Descent Calculational Model.
DOPEX-1D2CAbstractC00214 I0360 00A One-Dimensional, Two-Constraint Radiation Shield Optimization Code System.
DOQDPAbstractP00110 I0360 00Discrete Ordinates Quadrature Generator.
DORGLIBAbstractP00181 I0360 00An Interactive Program for Displaying Nuclide Decay and Generation Data Based on ORIGEN Data Library.
DORIANAbstractP00425 IBMPC 00Code System to Implement Bayes Method for Plant Aging Risk Analysis.
DOSCOVAbstractD00090 I0360 0024-Group Covariance Data.
DOSDAM77-81AbstractD00081 C6400 00620 Group, SAND-II Formatted, Neutron Cross Sections Based on ENDF/B-IV and Other Sources for Spectral, Integral, and Damage Analyses.
DOSDAM81-82AbstractD00097 C0000 00Multigroup Cross Sections in SAND-II Format for Spectral, Integral, and Damage Analyses.
DOSDAM84AbstractD00131 IBMMF 00Multigroup Cross Sections in SAND-II Format for Spectral, Integral, and Damage Analyses.
DOSDAT II-81AbstractD00079 I0370 00Dose-Rate Conversion Factors for External Exposure to Photons and Electrons.
DOSDAT-DOEAbstractD00144 ALLMF 00Dose-Rate Conversion Factors for External Exposure to Photons and Electrons.
DOSDAT-DOEAbstractD00144 IBMPC 01Dose-Rate Conversion Factors for External Exposure to Photons and Electrons.
DOSE 1AbstractC00165 I3675 00Gamma-Radiation Dosimetry for Arbitrary Source and Target Geometry.
DOSE-SGTRAbstractC00624 IBMPC 00Code System to Calculate the Integrated Iodine Release to the Environment During a Steam Generator Tube Rupture in a PWR.
DOSFACTER IIAbstractC00400 D0750 00Calculation of Dose-Rate Conversion Factors for Exposure to Photons and Electrons.
DOSFACTER IIAbstractC00400 I0360 00Calculation of Dose-Rate Conversion Factors for Exposure to Photons and Electrons.
DOSFACTER-DOEAbstractC00536 I3033 00Calculation of Dose-Rate Conversion Factors for Exposure to Photons and Electrons.
DPCTAbstractC00580 CYXMP 00A Deterministic-Probabilistic Model For Contaminant Transport.
DPL-400 GEDT1AbstractD00031 I0360 08Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format.
DPL-401 NEDTAbstractD00031 I0360 09Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format.
DPL-402A/GPDT1AbstractD00031 I0360 10Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format.
DPL-402B/GPDT1AbstractD00031 I0360 11Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format.
DRAGON2PARTISNAbstractC00803 PCX86 00Cross-Sections Data Generation for PARTISN4.0.
DRAGON3.05DAbstractC00647 MNYWS 03Lattice Cell Code System.
DRALISTAbstractD00080 ALLCP 00Radioactive Decay Data for Application to Radiation Dosimetry and Radiological Assessments.
DSNPAbstractP00592 I3033 00Dynamic Simulation Nuclear Power.
DSNQUADAbstractP00251 IPCXT 00Calculates Angular Quadrature Weights and Cosines.
DTF-69AbstractC00130 C6600 00One-Dimensional Multigroup Photon Transport Discrete Ordinates Code System.
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 00One-Dimensional Multigroup Neutron Transport Discrete Ordinates Code System.
DTKAbstractC00223 I3675 00One-Dimensional Multigroup Neutron Transport Code System.
DUFOLDAbstractP00042 I0360 00Derivative Unfolding Code - Determination of Neutron Spectra from NE-213 Pulse Height Data.
DUSTAbstractC00453 I3033 00Albedo Monte Carlo Simulation of Neutron Streaming Through Multilegged Ducts.
DUST-BNLAbstractC00634 PC386 00Disposal Unit Source Term by One-Dimensional, Transient, Finite-Difference, Subsurface Release and Transport of Contaminants.
DWBA07/DWBB07AbstractP00338 MNYCP 01Code System for Inelastic and Elastic Scattering with Nucleon-Nucleon Potential
DWNWNDAbstractC00383 DP010 00Interactive Gaussian Plume Atmospheric Transport Model.
DWUCK-CHUCKAbstractP00546 MNYCP 00Nuclear Model Code System for Distorted Wave Born Approximation and Coupled Channel Calculations.
DYN3D/M2AbstractP00579 I3090 00Reactivity Transients in Light H2O Reactors with Hexagonal Geometry.
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.