RSICC Catalog

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
RUGA -- Restricted Use Government Authorized
USSO -- US Distribution Only
USUNV -- US Universities Only

Packages with Keyword: MULTIGROUP CROSS SECTION PROCESSING
Package Name	Abstract	RSICC Tapelist	Title
CALENDF-2010 OECD	Abstract	P00578 PCX86 00	Pointwise, Multigroup Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations.
MC**2-2	Abstract	P00350 SUN05 01	Multigroup Cross Section Generation Code for Fast Reactor Analysis.
MC**2-3	Abstract	P00577 MNYCP 00	Multigroup Cross Section Generation Code for Fast Reactor Analysis.
MC**2-3 EXE	Abstract	P00577 MNYCP 01	Multigroup Cross Section Generation Code for Fast Reactor Analysis.
NJOY97.0	Abstract	P00368 MNYCP 00	Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
NJOY99.0	Abstract	P00480 MNYCP 00	Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
PREPRO2019	Abstract	P00351 MNYCP 10	Pre-Processing Code System for Data in ENDF/B Format.
PUFF-IV	Abstract	P00534 MNYCP 01	Determination of Multigroup Covariance Matrices from ENDF/B-V Uncertainty Files.
VITENEA-E	Abstract	D00240 MNYCP 00	AMPX 175-n,42-g Multigroup X-section Library for Nuclear Fusion Applications.
VITJEF22.BOLIB	Abstract	D00241 MNYCP 00	JEF-2.2 Multigroup Coupled (199n + 42?) Cross-Section Library in AMPX Format for Nuclear Fission Applications.

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