Online Catalog
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Note: RESTRICTIONS APPLY TO SOME PACKAGES -
810 -- US DOE 10CFR810 Jurisdiction
FEDC -- US Government Agencies and Their Contractors Only
OECD -- Restricted/See Abstract
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Packages with Keyword: OPTIMIZATION
Package NameAbstractRSICC TapelistTitle
ASOPAbstractC00126 IRISC 00Multigroup One-Dimensional Discrete Ordinates Transport Code System for Shield Optimization.
BEST-5AbstractP00591 I0370 00Power Reactor Fuel Cycle Optimization by Bellman Method.
CASKCODESAbstractP00262 IBMPC 00CAPSIZE, SCOPE, AND KWIKDOSE for Shipping Cask Optimization, Dose Calculation, Parameter Evaluation, and Shielding Requirements.
DOPEXAbstractC00177 I3675 00Laminated Shield Weight Optimization Code System-Steepest Descent Calculational Model.
DOPEXAbstractC00177 U1108 00Laminated Shield Weight Optimization Code System-Steepest Descent Calculational Model.
DOPEX-1D2CAbstractC00214 I0360 00A One-Dimensional, Two-Constraint Radiation Shield Optimization Code System.
FORISTAbstractP00092 C0000 00Neutron Spectrum Unfolding Code System - Iterative Smoothing Technique.
FORISTAbstractP00092 I0360 00Neutron Spectrum Unfolding Code System - Iterative Smoothing Technique.
MAX-XTREMEAbstractP00001 C0000 00Generalized Several-Constraint LaGrange Multiplier.
NUFACEAbstractP00284 CYXMP 00An Interface Code For The Calculation of Nuclear Responses.
OPEX-IIAbstractC00103 I7090 00Radiation Shield Optimization Code.
PELINOMIC-3AAbstractP00596 I0370 00Power Plant Cost Optimization for Dispersed Load Centers.
SCOPEAbstractP00210 I3033 00Computer Code System for Shipping Cask Optimization and Parametric Evaluation.
SWANAbstractC00248 C0000 00Code System for Analysis and Optimization of Fusion Reactor Nucleonic Characteristics.
SWANAbstractC00248 CY000 00Code System for Analysis and Optimization of Fusion Reactor Nucleonic Characteristics.
SWANAbstractC00248 I0360 00Code System for Analysis and Optimization of Fusion Reactor Nucleonic Characteristics.
TRAXAbstractP00280 C0720 00A Program For Optics of Curved Crystal Neutron Spectrometers.
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.