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: FISSION PRODUCT CROSS SECTIONS
Package NameAbstractRSICC TapelistTitle
DRALISTAbstractD00080 ALLCP 00Radioactive Decay Data for Application to Radiation Dosimetry and Radiological Assessments.
LUMPAbstractD00089 I0360 00Evaluated Lumped Fission Product Cross Sections for Fast Reactor Analysis--Based on ENDF/B-V Data.
MCB63NEA.BOLIBAbstractD00216 MNYCP 00ENDF/B-VI Release 3 Cross Section Library for Use with the MCNP Monte Carlo Code.
MCJEF22NEA.BOLIBAbstractD00203 MNYCP 01JEF 2.2 Cross Section Library for the MCNP Monte Carlo Code.
UKNDL-81AbstractD00107 I3033 00The Aldermaston Nuclear Data Library.
UTXS6AbstractD00211 MNYCP 00MCNP Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1365K.
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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.