Online Catalog
Click on Package Name to get detailed information.
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 with Keyword: MICROCOMPUTER
Package NameAbstractRSICC TapelistTitle
1DB-2DB-3DBAbstractC00741 PC586 00One-Dimensional Diffusion Code System for Nuclear Reactor.
ABAREXAbstractP00248 MNYCP 01Neutron Spherical Optical-Statistical Model Code System.
ABBN-90AbstractD00182 MNYCP 00Multigroup Constant Set for Calculation of Neutron and Photon Radiation Fields and Functionals, Including the CONSYST2 Program.
ACTIV-PCAbstractP00287 IBMPC 00A Program to Process Gamma or X-ray Spectra.
ADASAGEAbstractP00426 IBMPC 00Ada Application Development System.
ALBEDO/ALBEZAbstractC00555 IBMPC 00Calculates Attenuation of Radiation in Single and Double Bends.
ALDOSEAbstractC00577 IBMPC 00Dose Calculation for Alpha Disc Source.
ALKASYS-PCAbstractC00558 IBMPC 00A Computer Program For Studies of Rankine-Cycle Space Nuclear Power Systems.
ALPHNAbstractC00612 IBMPC 00Code System for Calculating (alpha,n) Neutron Production in Canisters of High-Level Waste.
ANAAbstractP00356 IBMPC 00Code System for Gamma-Ray Spectra Analyses.
ANISN-ORNLAbstractC00254 MNYCP 02One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering.
ANS643AbstractD00129 IBMPC 02Geometric Progression Gamma-Ray Buildup Factor Coefficients.
APUD 3.0AbstractC00637 IBMPC 00Code System for Analyzing, Predicting Consequences of, and Guiding the Response to Nuclear Emergencies.
AXMIX-PCAbstractP00297 IBMPC 00ANISN Cross Section Mixing Code System.
BASACFAbstractP00285 IBMPC 00Bayesian Approach to Spectrum Adjustment with Covariance Filter.
BETA-S 6AbstractC00657 MNYCP 01Code System to Calculate Multigroup Beta-Ray Spectra.
BLOCKAGE V2.5RAbstractP00377 IBMPC 00Code System to Calculate Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in a BWR.
BLT-FEMWATER
USSO
AbstractC00633 PC386 00Code System to Solve for Release and Transport of Contaminants through Saturated/Unsaturated Media.
BUCORSTAbstractP00339 PC386 00A Code to Prepare Burnup-Dependent Multigroup Nuclear Reactor Source Terms.
BUGLE-80AbstractD00075 IBMPC 03Coupled Neutron, Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications.
BUGLE-80AbstractD00075 PC386 01Coupled Neutron, Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications.
CALKUXAbstractC00594 IBMPC 00Code System to Calculate Exposure Transmission of Medical X-ray Beams Through Barrier Materials.
CAMERAAbstractC00240 C0074 00Radiation Transport Analysis Code System and the Computerized Man (CAM) Model.
CAMERAAbstractC00240 IBMPC 01Radiation Transport Analysis Code System and the Computerized Man (CAM) Model.
CAP-88AbstractC00542 D0VAX 00Clean Air Act Assessment Package.
CAP-88AbstractC00542 I3090 00Clean Air Act Assessment Package.
CAP-88AbstractC00542 IBMPC 00Clean Air Act Assessment Package.
CAP88-PCAbstractC00542 IBMPC 01Clean Air Act Assessment Package.
CASKAbstractD00023 I3691 0422 Neutron, 18 Gamma-Ray Group, P3, Cross Sections for Shipping Cask Analysis.
CASK-81AbstractD00023 I0370 0522 Neutron, 18 Gamma-Ray Group, P3, Cross Sections for Shipping Cask Analysis.
CASK-81AbstractD00023 IBMPC 0622 Neutron, 18 Gamma-Ray Group, P3, Cross Sections for Shipping Cask Analysis.
CEPXS/ONELD 1.0AbstractC00544 MNYCP 02One-Dimensional Coupled Electron-Photon Multigroup Discrete Ordinates Code System.
CHAINS-PCAbstractC00604 IBMPC 00Code System to Compute Atom Density of Members of a Single Decay Chain.
CHARGE IIAbstractC00070 C6500 00Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres.
CHARGE IIAbstractC00070 I3675 00Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres.
CHARGE-PCAbstractC00070 IBMPC 00Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres.
CHENDF 7.02AbstractP00333 MNYCP 05Codes for Handling ENDF/B-V and ENDF/B-VI Data.
CITATION-LDI 2AbstractC00643 PC386 02Nuclear Reactor Core Analysis Code System.
COMBINE-PCAbstractP00286 IBMPC 00Code System to Compute Neutron Spectra and ENDF/B Version 5 Based Multigroup Neutron Constants.
COMIDAAbstractP00343 MNYCP 00Radionuclide Food Chain Model for Acute Fallout Deposition.
COMPASS 1.0.0AbstractP00520 PC586 00Computerization of MARSSIM for Planning and Assessing Site Surveys.
CRRISAbstractC00518 I3033 00Computerized Radiological Risk Investigation System for Assessing Doses and Health Risks from Atmospheric Releases of Radionuclides.
CRRISAbstractC00518 PC586 00Computerized Radiological Risk Investigation System for Assessing Doses and Health Risks from Atmospheric Releases of Radionuclides.
DCHAIN 1.3AbstractC00640 MNYCP 01Code System for Radioactive Decay and Reaction Chain Calculations.
DCTDOSAbstractC00520 IBMPC 00Neutron and Gamma-Ray Penetration in Composite Duct Systems.
DECDC 1.0AbstractD00213 MNYCP 00Nucear Decay Data Files for Radiation Dosimetry Calculations.
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.
DIFBASAbstractP00334 MNYCP 00A Bayesian Approach to Unfolding a Neutron Spectrum from a Spectrum of Recoiled Protons.
DIMENAbstractP00341 IBMPC 00Code System for Isotope Identification by Gamma-Ray Analysis.
DOMUSAbstractP00301 IPCXT 00A Program for Decomposing A Two-Dimensional Spectrum.
DOSE-SGTRAbstractC00624 IBMPC 00Code System to Calculate the Integrated Iodine Release to the Environment During a Steam Generator Tube Rupture in a PWR.
DUST-BNLAbstractC00634 PC386 00Disposal Unit Source Term by One-Dimensional, Transient, Finite-Difference, Subsurface Release and Transport of Contaminants.
EGS4AbstractC00331 MNYCP 00Monte Carlo Simulation of the Coupled Transport of Electrons and Photons.
EQUIVA-1.1AbstractP00323 IMFPC 00Generation of Environment-Insensitive Equivalent Diffusion Theory Parameters for PWR Reflector Regions.
EQUIVA-2AbstractP00324 IMFPC 00Generation of Environment-Insensitive Equivalent Diffusion Theory Parameters for PWR Reflector Regions.
FASTPLOT 1.0AbstractP00354 IBMPC 00Interface to Microsoft FORTRAN Graphics.
FCXSECAbstractD00085 PC386 0122 Neutron, 21 Gamma-Ray Group Cross Section Libraries in ANISN Format for Nuclear Fuel Cycle Shielding Calculations.
FDMXPCAbstractP00322 IPCAT 00Code System for Calculation of Neutron Transmission and Other Functionals from Evaluated Data in ENDF Format.
FEDGROUP-RAbstractP00349 MNYCP 00Code System for Processing Evaluated Nuclear in ENDF/B, KEDAK or UKNDL Formats into Constants for Reactor Physics Calculation.
FEMWASTE/FEMWATERAbstractC00451 C7600 00A Finite-Element Model of Waste and Water Transport through Porous Saturated-Unsaturated Media.
FEMWASTE/FEMWATERAbstractC00451 PC386 00A Finite-Element Model of Waste and Water Transport through Porous Saturated-Unsaturated Media.
FERD-PCAbstractP00273 IBMPC 00Interactive Multichannel Neutron and Gamma-Ray Spectrum Matrix Unfolding Code System.
FLYSPEC-SHORTSAbstractP00196 C7600 00Neutron Unfolding Code System for Reducing Proton-Recoil Pulse-Height Obtained with NE-213 Liquid Scintillator.
FPZDAbstractC00603 PC386 00Code System for Multigroup Neutron Diffusion/Depletion Calculations.
FRANCOAbstractP00363 MNYCP 00Finite Element Fuel Rod Analysis Code System.
GCIAbstractP00421 IBMPC 00Generic Communications Index
GENII 2.10AbstractC00737 PCX86 02Environmental Radiation Dosimetry Software System.
GGG-GPAbstractC00564 IBMPC 00Kernel Integration Code System - Multigroup Gamma-Ray Scattering Using the GP Buildup Factor.
GIPAbstractP00229 IBMPC 00Group-Organized Cross-Section Input Program.
GMAAbstractP00367 MNYCP 00Code System for Calculation of Reactor Accident Consequences.
GNOMERAbstractC00625 MNYCP 01Multigroup 3-Dimensional Neutron Diffusion Nodal Code System with Thermohydraulic Feedbacks.
GUI2QAD-3DAbstractC00697 PC586 01A Graphical User Interface for QAD-CGPIC, a Point Kernal Code for Neutron and Gamma-Ray Shielding Calculations in Complex Geometry.
HABIT 1.1AbstractC00665 IBMPC 01Code System for Evaluation of Control Room Habitability.
HEATING 7.3AbstractP00199 MNYCP 06Multidimensional, Finite-Difference Heat Conduction Analysis Code System.
HILO86AbstractD00119 I0360 0066 Neutron, 22 Gamma-Ray Group Cross Sections for Radiation Transport for Neutron Energies Up to 400 MeV.
HILO86AbstractD00119 PC386 0166 Neutron, 22 Gamma-Ray Group Cross Sections for Radiation Transport for Neutron Energies Up to 400 MeV.
HILO86RAbstractD00187 ALLCP 0066 Neutron, 22 Gamma-Ray Group Cross Sections for Radiation Transport for Neutron Energies Up to 400 MeV.
HOTSPOT 3.0.2AbstractM00009 IBMPC 03Health Physics Code System for Evaluating Accidents Involving Radioactive Materials.
HPPOS 1.5AbstractD00173 IBMPC 00Health Physics Position Database.
HPPOS V2AbstractD00173 IBMPC 01Health Physics Position Database.
ICARAbstractP00291 IPCAT 00A Code For Combinatorial Calculation of Level Densities.
ICOMAbstractC00651 PC386 00Code System for Calculating Ion Track Condensed Collision Model.
INFLTBAbstractP00313 ALLCP 00Gamma-Ray Absorption Coefficient Calculation.
IRDAMAbstractC00524 IPCXT 00Interactive Rapid Dose Assessment Model.
ISO-PC 2.1AbstractC00636 IBMPC 01Kernel Integration Code System for General Purpose Isotope Shielding Analyses.
KENO2MCNPAbstractP00541 PC586 00Conversion of Input Data between KENO V.a and MCNP File Formats.
KUXAbstractC00515 ALLCP 00Medical X-Ray Shielding Calculation.
LABAN-PELAbstractC00611 IMFPC 00A Two-Dimensional, Multigroup Diffusion, High-Order Response Matrix Code.
LINEDOSEAbstractC00468 IBMPC 00A Line Source Shielding Code for Personal Computers.
LPTAUAbstractP00340 MNYCP 00Quasi-Random Sequence Generators.
LSHINSEAbstractC00554 IBMPC 00Calculates Flux and Dose Rate from the Scattering of Radiation in Air.
LSL-M2AbstractP00233 D6220 00Least-Squares Logarithmic Adjustment of Neutron Spectra.
LSL-M2AbstractP00233 IBMPC 00Least-Squares Logarithmic Adjustment of Neutron Spectra.
LSMOD-GLSMODAbstractP00342 IBMPC 00A Least-Squares Computational Tool Kit.
LTCAbstractP00329 IBMPC 00LMR Transient Calculation Code System.
MARLOWE 15BAbstractP00137 MNYCP 08Computer Simulation of Atomic Collisions in Crystalline Solids.
MARMERAbstractC00579 D8350 00A Flexible Point-Kernel Shielding Code System.
MARMERAbstractC00579 PC486 00A Flexible Point-Kernel Shielding Code System.
MCNP-DSP
810
AbstractC00699 MNYCP 00Monte Carlo N-Particle Transport Code System with Digital Signal Processing based on MCNP4A.
MCNP-DSP-EXE
810
AbstractC00699 MNYCP 01Monte Carlo N-Particle Transport Code System with Digital Signal Processing based on MCNP4A.
MCNPX-POLIMI
810
AbstractC00791 MNYCP 00Monte Carlo N-Particle Transport Code System To Simulate Time-Analysis Quantities.
MCNPX-POLIMI-EXE
810
AbstractC00791 MNYCP 01Monte Carlo N-Particle Transport Code System To Simulate Time-Analysis Quantities.
MCRACAbstractC00562 IBMPC 00Multiple Cycle Reactor Analysis Code.
MICROX-2AbstractP00374 MNYCP 02Code System to Create Broad-Group Cross Sections with Resonance Interference and Self-Shielding from Fine-Group and Pointwise Cross Sections.
MILDOS-AREAAbstractC00608 IBMPC 00Calculation of Radiation Dose from Uranium Recovery Operations for Large-Area Sources.
MOCAAbstractC00590 IPCAT 00Monte Carlo Criticality Code System for Hexagonal Geometries.
MONTEBURNS 2.0AbstractP00455 MNYCP 02Automated, Multi-Step Monte Carlo Burnup Code System.
MORSE-CGAAbstractC00474 ALLCP 03Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-EMPAbstractC00588 IBMPC 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MRIPP 1.0
810
AbstractC00655 PC386 00Magnetic Resonance Image Phantom Code System to Calibrate in vivo Measurement Systems.
MSM-SOURCEAbstractP00369 MNYCP 00Code System for Generation of Input Data for MCNP.
NACAbstractC00164 C0000 00Neutron Activation Analysis and Product Isotope Inventory Code System.
NACAbstractC00164 IBMMF 00Neutron Activation Analysis and Product Isotope Inventory Code System.
NAC-PCAbstractC00164 IBMPC 00Neutron Activation Analysis and Product Isotope Inventory Code System.
NCRP49AbstractC00462 IBMPC 00X-Ray Shield Calculation System.
NJOY97.0AbstractP00368 MNYCP 00Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
NJOY99.0AbstractP00480 MNYCP 00Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
NUCDECAYAbstractD00172 PC386 01Nuclear Decay Data for Radiation Dosimetry Calculations for ICRP and MIRD.
NUCDECAYCALCAbstractD00202 PC586 00Nuclear Decay Data for Radiation Dosimetry Calculations for ICRP.
ORIGEN2.2AbstractC00371 ALLCP 03Isotope Generation and Depletion Code - Matrix Exponential Method.
ORIGEN-JENDL32AbstractC00703 MNYWS 00Isotope Generation and Depletion Code - Matrix Exponential Method.
ORMONTEAbstractP00275 IBMPC 00Uncertainty Analysis Code System for Use with User-Developed Systems Models.
ORPLOT-PCAbstractP00328 PC386 00Plotting Package for Data Evaluation Intercomparison.
PAGANAbstractC00621 IBMPC 00Code System for Performance Assessment Ground-water Analysis for Low-level Nuclear Waste.
PARET-ANLAbstractP00516 MNYCP 00Code System to Predict Consequences of Nondestructive Accidents in Research and Test Reactor Cores.
PARET-ANL(NESC)AbstractP00565 MNYCP 00Code System to Predict Consequences of Nondestructive Accidents in Research and Test Reactor Cores.
PART61AbstractC00499 IBMPC 01Low-Level Radioactive Waste Impacts Analysis System.
PEGASAbstractP00336 IBMPC 00Pre-Equilibrium-Equilibrium Gamma-and-Spin Code System.
PEQAG-2AbstractP00293 IPCAT 00A Pre-equilibrium Computer Code With Gamma Emission.
PHOTXAbstractD00136 D0VAX 01Photon Interaction Cross Section Library.
PHOTXAbstractD00136 IBMPC 00Photon Interaction Cross Section Library.
PLOTTAB-89.1AbstractP00274 ALLCP 00Plot Continuous Curves or Discrete Points.
PRE-ANISNAbstractP00332 PC386 00A Preprocessing Code for ANISN and Other Radiation Transport Codes.
PR-EDBAbstractD00196 IBMPC 03Power Reactor Embrittlement Data Base.
PRISIMAbstractC00574 IBMPC 00Plant Risk Status Information Management System.
PSU-LEOPARD/RBIAbstractC00563 IBMPC 01A Spectrum Dependent Non-Spatial Depletion Code.
PTRANAbstractC00618 PC386 00Proton Monte Carlo Transport Program for the PC.
QAD-CGGP-AAbstractC00645 MNYCP 00Kernel Integration Code System.
QADMOD-GPAbstractC00565 IBMPC 00Point Kernel Gamma-Ray Shielding Code With Geometric Progression Buildup Factors.
QBFAbstractC00617 PC386 00Code System to Calculate Radiation Dose Rates Relative to Spent Fuel Shipping Casks.
QBSHIELDAbstractC00599 IBMPC 00Spherical Shield Design for Gamma-Ray Sources Using the Buildup Factor Method.
QUINCE-PCAbstractC00556 IBMPC 00Calculates Absorbed Dose From Skin Contamination.
RADACAbstractC00627 PC486 02Code System for Calculating Radioactive Decay and Accumulation of Decayed Products Using Integer-Array Arithmetic for Precise Evaluation of the Bateman Equations.
RADCOMPT 2.10LAbstractP00348 IBMPC 00Sample Analysis Code System for the Dual Channel Counter.
RASCAL 4.3AbstractC00783 PCX86 02Radiological Assessment for Consequence Analysis.
RBDAbstractC00632 IBMPC 00U.S. Army Radiological Bioassay and Dosimetry.
RCSLK9AbstractP00452 IBMPC 00Code System to Calculate Reactor Coolant System Leak Rate.
REAC*3AbstractC00443 IBMPC 00Computer Code System for Activation and Transmutation.
REAC*3AbstractC00443 MFMWS 00Computer Code System for Activation and Transmutation.
REACTIONAbstractP00347 AL000 00Code System to Calculate Integral Parameters with Reaction Rates from WIMS Output.
REACTIONAbstractP00347 IBMPC 00Code System to Calculate Integral Parameters with Reaction Rates from WIMS Output.
REBUS3/VARIANT8AbstractC00653 MNYWS 01Code System for Analysis of Fast Reactor Fuel Cycles.
REPRISK PC 1.02AbstractC00586 PC386 01Repository Risk Assessment Software for Personal Computers.
RISKIND 2.0
FEDC
AbstractC00623 IBMPC 02Radiological Risk Assessment Code System for Spent Nuclear Fuel Transportation.
RIVER-RADAbstractC00626 MNYCP 00Code System for Simulating the Transport of Radionuclides in Rivers.
RSAC-7.2AbstractC00761 PC586 01Radiological Safety Analysis.
SAILORAbstractD00076 PC386 01Coupled, Self-Shielded, 47 Neutron, 20 Gamma-Ray, P3, Cross Section Library for Light Water Reactors.
SAIPS-PCAbstractP00295 IBMPC 00Information Processing System for Calculating Neutron Spectra from Measured Reaction Rates.
SAND-IIAbstractC00112 MNYCP 03Neutron Flux Spectra Determination by Multiple Foil Activation Method.
SCAT-2AbstractP00294 MNYCP 03Code System for Calculating Total and Elastic Scattering Cross Sections Based on an Optical Model of the Spherical Nucleus.
SESOILAbstractC00629 IBMPC 03Code System to Calculate One-Dimensional Vertical Transport for the Unsaturated Soil Zone.
SHIELDOSEAbstractC00379 ALLMF 00Code System for Space Shielding Radiation Dose Calculations.
SHIELDOSE-PCAbstractC00379 IBMPC 00Code System for Space Shielding Radiation Dose Calculations.
SIGMA IIAbstractC00118 C6000 00Space Radiation Dose Analysis Within Complex Configurations.
SIGMA IIAbstractC00118 PC486 00Space Radiation Dose Analysis Within Complex Configurations.
SIGMA-AAbstractD00139 ALLMF 00Photon Interaction and Absorption Cross Sections.
SIGMA-AAbstractD00139 IBMPC 00Photon Interaction and Absorption Cross Sections.
SKYDATA-KSUAbstractD00188 IBMPC 00Parameters for Approximate Neutron and Gamma-Ray Skyshine Response Functions and Ground Correction Factors.
SKYIII-PCAbstractC00289 IBMPC 01Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air.
SKYSHINE-IIIAbstractC00289 D0VAX 00Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air.
SKYSHINE-KSUAbstractC00646 IBMPC 03Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air.
SLIDERULE 1.0AbstractC00704 PC586 01Nuclear Criticality Slide Rule.
SMARTAbstractC00602 ALLCP 00Code System for Calculating Early Offsite Consequences from Nuclear Reactor Accidents.
SOURCES-4CAbstractC00661 MNYCP 04Code System for Calculating (alpha,n), Spontaneous Fission, and Delayed Neutron Sources and Spectra.
STAPREFAbstractP00498 PC586 00Code System to Calculate Nuclear Reaction Cross Sections by Evaporation Model.
STAPRE-H95AbstractP00325 MNYCP 01Code System to Calculate Energy-Averaged Cross Sections of Particle Induced Nuclear Reactions.
STAR CODESAbstractP00330 IBMPC 00Code System for Calculating Stopping-Power and Range Tables for Electrons, Protons, and Helium Ions.
SUPERDAN-PCAbstractP00282 IBMPC 00Calculates Dancoff Factor of Spheres, Cylinders and Slabs.
TART2016AbstractC00638 MNYCP 08Coupled Neutron-Photon, 3-D, Combinatorial Geometry, Time Dependent, Monte Carlo Transport Code System.
TIBSOAbstractC00512 MNYCP 00Code System to Calculate Production and Migration of Radionuclides in Nuclear Reactor Systems.
TRIGAPAbstractC00600 IBMPC 00A Computer Code for TRIGA Type Reactors.
UKFY2AbstractD00171 IBMPC 00UK Fission Product Yield Library.
UPEAKAbstractP00300 IPCXT 00A Program for Decomposing A One-Dimensional Spectrum.
UPEML 3.0AbstractP00245 ALLCP 01A Machine-Portable CDC UPDATE Emulator.
VALE 1.1AbstractC00613 IRISC 01A Multigroup Diffusion Theory Neutronics Code System for Solving Two- and Three-Dimensional Problems for Triagonal Geometries.
VALE 1.1AbstractC00613 PC386 01A Multigroup Diffusion Theory Neutronics Code System for Solving Two- and Three-Dimensional Problems for Triagonal Geometries.
VENTURE-PCAbstractC00654 PC586 02A Reactor Analysis Code System.
VESTA 2.1.5-AURORA 1.0AbstractC00769 PCX86 01A Generic Monte Carlo Code and Depletion Module Interface.
VIDEO-PCAbstractP00311 IBMPC 00Super VGA Primitives Graphics System.
VPI-NECMAbstractC00481 C0740 00Nuclear Engineering Computer Models for In-Core Fuel Management Analysis.
VPI-NECMAbstractC00481 D0VAX 00Nuclear Engineering Computer Models for In-Core Fuel Management Analysis.
VPI-NECMAbstractC00481 PC486 00Nuclear Engineering Computer Models for In-Core Fuel Management Analysis.
WILITAbstractP00344 MNYCP 00A Utility Program for WIMS Libraries.
WIMSD-5B.12AbstractC00656 MNYCP 02Deterministic Code System for Reactor Lattice Calculation
XCOMAbstractD00174 IBMPC 00Photon Cross Sections on a Personal Computer.
XG-IAEAAbstractD00163 IBMPC 00X-ray and Gamma-ray Standards For Detector Calibration.
XPORT-PCAbstractC00559 IBMPC 00An Approximation For Black Body X-Ray Transport in Air.
XSHLDAbstractC00495 IBMPC 00Diagnostic X-Ray Shielding Calculation.
ZOTT99AbstractP00272 ALLCP 02Zero-in On The Truth; Evaluation of Correlated Data Using Partitioned Least Squares.
ZYLIND-PCAbstractC00557 IBMPC 00An Interactive Point Kernel Program For Photon Dose Rate Prediction of Cylindrical Source/Shield Arrangements.
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.