RSICC Catalog

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: KERMA FACTORS
Package Name	Abstract	RSICC Tapelist	Title
BUGLE-93	Abstract	D00175 ALLCP 01	Coupled Neutron, Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications.
BUGLE-96	Abstract	D00185 ALLCP 00	Coupled Neutron, Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications.
DABL69	Abstract	D00130 I0360 01	Defense Nuclear Applications Broad-Group Library based on ENDF/B-V in ANISN Format.
EPR	Abstract	D00037 I3691 05	Coupled 100-Group Neutron 21-Group Gamma-ray Cross Sections for EPR Neutronics.
FLUKA05-PRE-LIB	Abstract	D00260 PCX86 00	FLUKA05 Multi-Group, Multi-Purpose Nuclear Data Library, Neutrons, Photons, Charged Particles.
KAOS/LIB-V	Abstract	D00160 CY000 00	A Library of Nuclear Response Functions Generated by KAOS-V Code From ENDF/B-V and Other Data Files.
KERMAL	Abstract	D00142 ALLCP 00	Neutron and Gamma-Ray Kerma Factors Based on LLNL Nuclear Data Files.
LAHIMACK	Abstract	D00128 I0360 00	A Multigroup Library of Neutron and Gamma Cross Sections and Response Functions in the Energy Range up to 800 MeV.
MACKLIB-IV-82	Abstract	D00060 I0360 01	A Library of Nuclear Response Functions Generated with the MACK-V Computer Program from ENDF/B-IV.
MATXS10	Abstract	D00176 ALLCP 00	Neutron, Photon Cross Sections from ENDF/B-IV in MATXS Format.
MATXS11	Abstract	D00177 ALLCP 00	Neutron, Photon Cross Sections from ENDF/B-IV in MATXS Format.
UKCTRI-81	Abstract	D00064 I0370 01	46-Group Neutron Cross Sections and Kerma Factors for Fusion Reactor Calculations.
VITAMIN-B7/BUGLE-B7	Abstract	D00245 MNYCP 01	Broad-Group and Fine-Group and Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data.
VITAMIN-J/KERMA	Abstract	D00150 I3090 00	Broad-Group and Fine-Group and Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data.

1 2 3 A B C D E F G H I J K L M N O P Q R S T U V W X Y Z

The Radiation Safety Information Computational Center (RSICC) is a Department of Energy Specialized Information Analysis Center (SIAC) authorized to collect, analyze, maintain, and distribute computer software and data sets in the areas of radiation transport and safety. RSICC resides in the Reactor and Nuclear Systems Division (RNSD) at Oak Ridge National Laboratory.