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
Package NameAbstractRSICC TapelistTitle
INFLTBAbstractP00313 ALLCP 00Gamma-Ray Absorption Coefficient Calculation.
KAOS-VAbstractP00306 CY000 00An Evaluation Tool For Neutron Kerma Factors and Other Nuclear Responses.
LOGNORMLAbstractP00307 IPCAT 00Lognormal Probability Analysis Code System for Estimating Doses in Epidemiologic Studies.
MACK-IVAbstractP00132 I3691 00Calculation of Nuclear Response Functions from Nuclear Data in ENDF Format.
NEVEMORAbstractP00026 I3675 00Multigroup-Multiregion Calculation of Flux Spectra and Energy Deposition for Fast Neutrons.
NJOY91.119AbstractP00171 MFMWS 04Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
NJOY94.61AbstractP00355 MFMWS 03Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
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.
NUFACEAbstractP00284 CYXMP 00An Interface Code For The Calculation of Nuclear Responses.
REPCAbstractP00195 C0000 00Estimation of Nuclear Reaction Effects in Proton-Tissue-Dose Calculations.
UNFAbstractP00521 PC586 00Code System to Calculate Multistep Compound Nucleus Neutron Cross-Sections and Spectra for Structural Materials.
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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.