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: COVARIANCE DATA PROCESSING
Package NameAbstractRSICC TapelistTitle
ACORNSAbstractP00264 IBMPC 01Analysis of Correlations Used in Neutron Spectrometry.
FERRETAbstractP00145 U0000 00Least-Squares Solution to Nuclear Data and Reactor Physics Problems.
GLUCSAbstractP00192 D0VAX 00A Generalized Least-Squares Code System for Updating Cross Section Evaluations with Correlated Data Sets.
LEPRICONAbstractP00277 I3033 01PWR Pressure Vessel Surveillance Dosimetry Analysis System.
LEPRICONAbstractP00277 IRISC 00PWR Pressure Vessel Surveillance Dosimetry Analysis System.
LSL-M2AbstractP00233 D6220 00Least-Squares Logarithmic Adjustment of Neutron Spectra.
LSL-M2AbstractP00233 IBMPC 00Least-Squares Logarithmic Adjustment of Neutron Spectra.
NJOY91.119AbstractP00171 MFMWS 04Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
NJOY94.61AbstractP00355 MFMWS 03Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
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.
PUFF-IVAbstractP00534 MNYCP 01Determination of Multigroup Covariance Matrices from ENDF/B-V Uncertainty Files.
STAY'SLAbstractP00113 DP010 00Least Squares Dosimetry Unfolding Code System.
STAYSL PNNLAbstractP00589 PCX86 00STAYSL PNNL Suite of Software Tools.
ZOTT99AbstractP00272 ALLCP 02Zero-in On The Truth; Evaluation of Correlated Data Using Partitioned Least Squares.
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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.