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 starting with K
Package NameAbstractRSICC TapelistTitle
K009AbstractC00062 I7090 00Solid Angle Integration Charged Particle Penetration Code.
K019AbstractC00100 I0360 00Shield Thickness Calculation Program for Space Vehicles.
KAMCCOAbstractC00325 I0370 00Three-Dimensional Time Dependent Monte Carlo Code System for Fast Neutron Physics Problems.
KAOS/LIB-VAbstractD00160 CY000 00A Library of Nuclear Response Functions Generated by KAOS-V Code From ENDF/B-V and Other Data Files.
KAOS-VAbstractP00306 CY000 00An Evaluation Tool For Neutron Kerma Factors and Other Nuclear Responses.
KAP-VIAbstractC00094 U1108 00Kernel Integration Code System in Complex Geometry.
KASYAbstractC00814 I0370 003-D Homogeneous Neutron Diffusion in X-Y-Z, R-Theta, Hexagonal-Z Geometry by Synthesis Method.
KCUTAbstractP00584 IBMPC 00Code to Generate Minimal Cut Sets for Fault Trees.
KDDKAbstractD00061 I0360 00Measured Results of Delayed Beta- and Gamma-Ray Spectra due to Thermal-Neutron Fission of U-235.
KDLIBEAbstractC00124 I3675 00Kernel-Diffusion Shielding Analysis System.
KEDAK3AbstractD00141 I0370 00Evaluated Neutron Nuclear Data for Reactor Physics Calculations.
KENO2MCNPAbstractP00541 PC586 00Conversion of Input Data between KENO V.a and MCNP File Formats.
KERMALAbstractD00142 ALLCP 00Neutron and Gamma-Ray Kerma Factors Based on LLNL Nuclear Data Files.
KERNELAbstractC00672 IBMPC 00Monte Carlo Code System for Electron (Positron) Dose Kernel Calculations.
KFIXAbstractP00409 C7600 00Code System to Calculate Transient 2-Dimensional 2-Fluid Flow Dynamics.
KFIX 3DAbstractP00383 C7600 00Code System to Calculate Three-Dimensional Extension Two-Phase Flow Dynamics.
KICHE 1.3AbstractC00796 PCX86 00Kinetics of Iodine Chemistry in the Containment of LWRs under Severe Accident Conditions.
KIMAbstractC00376 I3033 00A Two-Dimensional Monte Carlo Code System for Linear Neutron Transport Calculations.
KORIGENAbstractC00457 I3033 00A Modification of the Isotope Generation and Depletion Code System ORIGEN.
KRAKENAbstractC00877 PCX86 00Computational Reactor Analysis Framework.
KRONICAbstractC00229 I0360 00Calculation of Annual Average External (Beta and Gamma Radiation) Doses from Chronic Atmospheric Releases of Radionuclides.
KRONICAbstractC00229 U1108 00Calculation of Annual Average External (Beta and Gamma Radiation) Doses from Chronic Atmospheric Releases of Radionuclides.
KUXAbstractC00515 ALLCP 00Medical X-Ray Shielding Calculation.
KX-RAYAbstractD00021 I0360 00Evaluated X-ray Cross Section Library.
123ABCDEFGHIJKLMNOPQRSTUVWXYZ
FAQ | ORNL Home | DOE | Site Map | Security Notice
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.