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: MATXS FORMAT
Package NameAbstractRSICC TapelistTitle
FENDL-2.1AbstractD00222 MNYCP 00Compendium of Reference and Processed Sub-libraries Derived from International Evaluated Nuclear Data Files for Fusion Applications.
MATJEFF31.BOLIBAbstractD00242 MNYCP 00Fine-Group Cross Section Library Based on JEFF3.1 for Nuclear Fission Applications.
MATXS10AbstractD00176 ALLCP 00Neutron, Photon Cross Sections from ENDF/B-IV in MATXS Format.
MATXS11AbstractD00177 ALLCP 00Neutron, Photon Cross Sections from ENDF/B-IV in MATXS Format.
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.
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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.