Online Catalog
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Click on Abstract to read the package abstract.
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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 Subject: NUCLEAR DATA POST-PROCESSOR, GRAPHIC DISPLAY, CURVE FITTING
Package NameAbstractRSICC TapelistTitle
ANIPLO D50AbstractP00213 I0360 00A Digital Computer Program for Plotting Results from Calculations with the Sn Computer Program ANISN.
ANSIFTAbstractP00077 C6600 00ANSI Standard Fortran Sifting Program.
ANSIFTAbstractP00077 I0360 00ANSI Standard Fortran Sifting Program.
APSAIAbstractP00065 I3691 00Activity Calculations and Plotting of Neutron or Gamma-Ray Spectra Generated by Discrete Ordinates Code System ANISN.
BAYESAbstractP00205 DP010 00User's Guide for A General-Purpose Computer Code System for Fitting a Functional Form to Experimental Data.
BSPRP2AbstractP00372 IRISC 00Code System to Process DORT Boundary-Flux Files.
CHENDF 7.02AbstractP00333 MNYCP 05Codes for Handling ENDF/B-V and ENDF/B-VI Data.
DORGLIBAbstractP00181 I0360 00An Interactive Program for Displaying Nuclide Decay and Generation Data Based on ORIGEN Data Library.
EDITORAbstractP00035 I0360 00Alters Mode, Copies, Merges, Punches, Edits, or Adds to ENDF/B-Formatted Data on Tapes or Cards.
ENDVER/GUIAbstractP00572 PCX86 00The ENDF File Verification Support Package.
EZVIDEOAbstractP00237 IBMPC 00Graphics Routines for the IBM PC.
FASTPLOT 1.0AbstractP00354 IBMPC 00Interface to Microsoft FORTRAN Graphics.
FERRETAbstractP00145 U0000 00Least-Squares Solution to Nuclear Data and Reactor Physics Problems.
FLOWPLOT IIAbstractP00234 I3033 00Fluid Dynamics and Heat Transfer Plotting Package.
FLUSHAbstractP00043 C6600 00Spectral Unfolding Code - Stepwise Regression of System Response Functions.
FREEFORMAbstractP00081 I0360 00Free-Form Input Reading Routines.
GANDR/SEMOVEAbstractC00765 PCX86 00Program for Calculating Derivatives of Processed Multigroup Nuclear Data by Discrete Differences.
GOFRRAbstractP00127 I0360 00Generator of Graphical Output of DOT and ANISN Fluxes and Reaction Rates.
GRFPAKAbstractP00478 I0360 00Code System to Plot CORTES FEM Results.
INTRIGUE-IIAbstractP00054 I0360 00Logarithmic and Semilogarithmic CALCOMP Plot Routines.
KENO2MCNPAbstractP00541 PC586 00Conversion of Input Data between KENO V.a and MCNP File Formats.
LOUHI82AbstractP00236 U1108 00General Purpose Unfolding Program with Linear and Nonlinear Regularizations.
LSL-M2AbstractP00233 D6220 00Least-Squares Logarithmic Adjustment of Neutron Spectra.
LSL-M2AbstractP00233 IBMPC 00Least-Squares Logarithmic Adjustment of Neutron Spectra.
MAINTAINAbstractP00067 I0360 00Code System for Use in Maintaining and Revising Card Image Files on Tape.
MAZE IIAbstractP00041 U1108 00Spectral Unfolding Code.
MAZE-1AbstractP00041 C6600 00Spectral Unfolding Code.
MOCUPAbstractP00365 DALPU 00MCNP/ORIGEN Coupling Utility Programs.
MONTEBURNS 2.0AbstractP00455 MNYCP 02Automated, Multi-Step Monte Carlo Burnup Code System.
MRSPAKAbstractP00212 DVX11 00A Code System To Generate a Text File Containing Combinatorial Geometry Data Corresponding to PADL2 Geometry.
ORPLOT-PCAbstractP00328 PC386 00Plotting Package for Data Evaluation Intercomparison.
PICTUREAbstractP00238 IBMPC 00Combinatorial Geometry Printer Plotting.
PLOTENDFAbstractP00214 I3033 00A Program for Producing Graphical Output.
PLOTFBAbstractP00018 I3675 00ENDF/B Data Plotting Code.
PLOTNFITAbstractP00382 IBMPC 00Code System for Data Plotting and Curve Fitting.
PLOT-SAbstractP00552 PC586 00Plotting Program with Special Features for Windows Environment.
PREPRO2019AbstractP00351 MNYCP 10Pre-Processing Code System for Data in ENDF/B Format.
SAIPS-PCAbstractP00295 IBMPC 00Information Processing System for Calculating Neutron Spectra from Measured Reaction Rates.
SCOPEAbstractP00210 I3033 00Computer Code System for Shipping Cask Optimization and Parametric Evaluation.
SIOBAbstractP00139 I0360 00Calculation of Least-Squares Shape Fitting Several Neutron Transmission Measurements Using the Breit-Wigner Multilevel Formula.
STRADEAbstractP00252 I3081 00Stratified Random Design.
TPASSAbstractP00164 DP010 00A Gamma-Ray Spectral Data-Reduction and Analysis Code System.
TRANSX 2.15AbstractP00317 MFMWS 01Code system to produce neutron, photon, and particle transport tables for discrete-ordinates and diffusion codes from cross sections in MATXS format.
TRANSX-CTRAbstractP00206 CY000 00Interfaces MATXS Cross-Section Libraries to Nuclear Transport Codes for Fusion Systems Analysis.
UKE-IIIAbstractP00015 I3691 00Cross Section Format Translator - UKNDL to ENDF/B.
VIDEO-PCAbstractP00311 IBMPC 00Super VGA Primitives Graphics System.
VIEWCXSAbstractP00514 PC586 00Interactive Graphic User Interface to View Neutron and Gamma-Ray Interaction Cross Sections.
VIXENAbstractP00030 C6600 00A Code to Check Physical Consistency of Photon-Production Data in Revised ENDF Format.
VIXENAbstractP00030 I0360 00A Code to Check Physical Consistency of Photon-Production Data in Revised ENDF Format.
WLUP 3.0AbstractD00231 MNYCP 0169- and 172- Group Cross Section Libraries for WIMS.
The Radiation Safety Information Computational Center (RSICC) collects, analyzes, maintains, and distributes software in the areas of radiation transport and safety. RSICC resides in the Nuclear Energy and Fuel Cycle Division (NEFCD) at Oak Ridge National Laboratory.