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: MULTIGROUP CROSS SECTION PROCESSING
Package NameAbstractRSICC TapelistTitle
CALENDF-2010
OECD		AbstractP00578 PCX86 00Pointwise, Multigroup Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations.
MC**2-2AbstractP00350 SUN05 01Multigroup Cross Section Generation Code for Fast Reactor Analysis.
MC**2-3AbstractP00577 MNYCP 00Multigroup Cross Section Generation Code for Fast Reactor Analysis.
MC**2-3 EXEAbstractP00577 MNYCP 01Multigroup Cross Section Generation Code for Fast Reactor Analysis.
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.
PREPRO2019AbstractP00351 MNYCP 10Pre-Processing Code System for Data in ENDF/B Format.
PUFF-IVAbstractP00534 MNYCP 01Determination of Multigroup Covariance Matrices from ENDF/B-V Uncertainty Files.
VITENEA-EAbstractD00240 MNYCP 00AMPX 175-n,42-g Multigroup X-section Library for Nuclear Fusion Applications.
VITJEF22.BOLIBAbstractD00241 MNYCP 00JEF-2.2 Multigroup Coupled (199n + 42?) Cross-Section Library in AMPX Format for Nuclear Fission Applications.
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