Online Catalog
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810 -- US DOE 10CFR810 Jurisdiction
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Packages with Keyword: COMBINATORIAL GEOMETRY
Package NameAbstractRSICC TapelistTitle
ANTE 2AbstractC00131 I3675 00Adjoint Monte Carlo Time-Dependent Neutron Transport Code in Combinatorial Geometry.
CALOR95AbstractC00610 MNYWS 00Monte Carlo Code System for Design and Analysis of Calorimeter Systems, Spallation Neutron Source (SNS) Target Systems, etc.
EASY-QAD 2.0.1AbstractC00744 PC586 02A Visualization Code System for Gamma and Neutron Shielding Calculations.
GGG-GPAbstractC00564 IBMPC 00Kernel Integration Code System - Multigroup Gamma-Ray Scattering Using the GP Buildup Factor.
GUI2QAD-3DAbstractC00697 PC586 01A Graphical User Interface for QAD-CGPIC, a Point Kernal Code for Neutron and Gamma-Ray Shielding Calculations in Complex Geometry.
ITS6
FEDC
AbstractC00792 PCX86 00Integrated TIGER Series of Coupled Electron/Photon Monte Carlo Transport Codes System.
KIMAbstractC00376 I3033 00A Two-Dimensional Monte Carlo Code System for Linear Neutron Transport Calculations.
MORSE-ANSI STD.AbstractC00127 I3675 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-BAbstractC00368 I0370 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-CGAbstractC00203 C0000 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-CGAbstractC00203 CY000 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-CGAbstractC00203 D0VAX 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-CGAbstractC00203 I0360 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-CGAbstractC00203 U0000 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-CGAAbstractC00474 ALLCP 03Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSEC-SP2AbstractP00142 H6000 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-EMPAbstractC00588 IBMPC 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-HAbstractC00471 I3081 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
PUTZ 2.1AbstractC00595 IBMPC 00A Point-Kernel Photon Shielding Code.
QAD-CGGP-AAbstractC00645 MNYCP 00Kernel Integration Code System.
QAD-UEAbstractC00448 H6000 00Kernel Integration Code System.
SAM-CEAbstractC00187 C6600 00Monte Carlo Time-Dependent Complex Geometry (Combinatorial) Code System for the Solution of the Forward Neutron and Forward and Adjoint Gamma-Ray Transport Equations.
SAM-CEAbstractC00187 I0360 00Monte Carlo Time-Dependent Complex Geometry (Combinatorial) Code System for the Solution of the Forward Neutron and Forward and Adjoint Gamma-Ray Transport Equations.
SAM-CEPAbstractC00192 C6600 00Monte Carlo Code System Correlated to the Simultaneous Solution of Multiple, Perturbed, Time-Dependent Neutron Transport Problems in Complex Three-Dimensional Geometry.
VIM 5.1AbstractC00754 MNYWS 01Continuous Energy Neutron and Gamma-ray Transport Code System.
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.