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: ACTIVATION
Package NameAbstractRSICC TapelistTitle
AARE-V1.0AbstractC00846 MNYCP 00Activation in Accelerator Radiation Environments
ACAB-2008AbstractC00758 MNYCP 01Activation Abacus Inventory Code System for Nuclear Applications.
ACDOS3AbstractC00442 C7600 00Calculation of Activities and Dose Rates Produced by Neutron Activation.
ACFAAbstractC00478 I3033 00A Versatile Activation Code for Coolant and Structural Materials.
AKTIVAbstractC00339 I0360 00An Evaluation of Activity, Afterheat and Biological Hazard Potential of Stainless Steel Structures in Fusion Reactor Blankets.
ANITA-2000AbstractC00693 MNYCP 00Analysis of Neutron Induced Transmutation and Activation.
ANITA-4AbstractC00606 MNYCP 01Analysis of Neutron Induced Transmutation and Activation.
CARL 2.3AbstractC00743 PC586 01Code System to Calculate Radiotoxicity, Activity, Dose and Decay Power Calculations for Spent Fuel.
CINDER 1.05AbstractC00755 PC586 00Code System for Actinide Transmutation Calculations
COG11.1AbstractC00829 MNYCP 00Multiparticle Monte Carlo Code System for Shielding and Criticality Use.
DKRAbstractC00323 CY000 00A Radioactivity and Dose Rate Calculation Code System for Fusion Reactors.
FDKRAbstractC00541 I4381 00Radioactivity and Dose Rate Calculation Code for Fission, Fusion and Hybrid Reactors.
FISPACT-II 5.0AbstractC00836 MNYCP 03FISPACT-II 5.0 & TENDL-2019; TENDL-2017, -2015; ENDF/B-VIII.0, -VII.1; JENDL-4.0; JEFF-3.3, -3.2; CENDL-3.1; HEIR-0.1; HEAD-2009; and GEFY-6.1 libraries.
FISPINAbstractC00413 ICL00 00Nuclide Inventory Calculation System.
INAPAbstractC00235 U1108 00Improved Neutron Activation Prediction Code Systems.
MAGIKAbstractC00359 I0360 00A Monte Carlo Code System for Computing Induced Residual Activation Dose Rates.
MENDL-2PAbstractD00207 MNYCP 00Proton Reaction Data Library for Nuclear Activation (Medium Energy Nuclear Data Library.)
NAAPROAbstractC00722 PC586 00Neutron Activation Analysis PRognosis and Optimization Code System.
NACAbstractC00164 C0000 00Neutron Activation Analysis and Product Isotope Inventory Code System.
NACAbstractC00164 IBMMF 00Neutron Activation Analysis and Product Isotope Inventory Code System.
NAC-PCAbstractC00164 IBMPC 00Neutron Activation Analysis and Product Isotope Inventory Code System.
NACTAbstractC00502 U1100 00Screening Program for Neutron Activation Products.
NAPAbstractC00101 I7090 00Multigroup Time-Dependent Neutron Activation Prediction Code.
ORIP_XXIAbstractC00731 PC586 02Computer Programs for Isotope Transmutation Simulations.
PADF-2007AbstractD00259 PCX86 00Proton Activation Data File in ENDF-6 Format.
PATCH-7AbstractC00243 C0074 00Three-Dimensional Kernel Integration Code-Explicit Single Scattering Option.
RACCAbstractC00388 CY000 00A Code System for Computing Radioactivity-Related Parameters for Fusion Reactor Systems.
RACCAbstractC00388 I3033 00A Code System for Computing Radioactivity-Related Parameters for Fusion Reactor Systems.
RACC-PULSEAbstractC00639 MNYWS 00RACC Code System for Computing Radioactivity-Related Parameters for Fusion Reactor Systems Modified for Pulsed/Intermittent Activation Analysis.
REAC*3AbstractC00443 IBMPC 00Computer Code System for Activation and Transmutation.
REAC*3AbstractC00443 MFMWS 00Computer Code System for Activation and Transmutation.
SHARDAAbstractC00521 C0740 00Sample Heat, Activity, Reactivity, and Dose Analysis for Safety Analysis of Irradiations in a Research Reactor.
SOSUMAbstractC00109 I3675 00Multigroup Beta and Gamma-Ray Energy Sources from Activities.
THIDA-2AbstractC00410 FM380 00Code System for the Calculation of Transmutation, Activation, Decay Heat and Dose Rate in Fusion Reactors.
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.