RSICC Catalog

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: SENSITIVITY ANALYSIS
Package Name	Abstract	RSICC Tapelist	Title
ABLEIT-TRANS	Abstract	P00247 C0175 00	Error Propagation Analysis for Burnup Calculation.
ARC 11.2892 FEDC	Abstract	C00824 MNYCP 02	Code System for Analysis of Nuclear Reactors.
BOLD VENTURE IV	Abstract	C00459 I3033 00	A Reactor Analysis Code System.
ERANOS 2.0 OECD	Abstract	C00745 MNYWS 00	Modular Code and Data System for Fast Reactor Neutronics Analyses
ERRORJ	Abstract	P00526 MNYCP 03	Multigroup Covariance Matrices Generation from ENDF/B-6 Format.
FORSEN	Abstract	P00170 I0360 00	A Multigroup Processing Code for Use with Sensitivity Profiles to Assess the Effect of Cross Section Changes.
FORSS	Abstract	C00334 C0000 00	A Sensitivity and Uncertainty Analysis Code System.
FORSS	Abstract	C00334 I0360 00	A Sensitivity and Uncertainty Analysis Code System.
GANDR/SEMOVE	Abstract	C00765 PCX86 00	Program for Calculating Derivatives of Processed Multigroup Nuclear Data by Discrete Differences.
GRESS 3.0	Abstract	P00231 MFMWS 02	Gradient Enhanced Software System.
LEPRICON	Abstract	P00277 I3033 01	PWR Pressure Vessel Surveillance Dosimetry Analysis System.
LEPRICON	Abstract	P00277 IRISC 00	PWR Pressure Vessel Surveillance Dosimetry Analysis System.
NEUPAC	Abstract	P00177 FM200 00	Neutron Unfolding Code System for Calculating Neutron Flux Spectra from Activation Data of Dosimeter Foils.
PCC/SRC	Abstract	P00456 D0VAX 00	Code System to Calculate Correlation & Regression Coefficients.
PERSENT 11.2892 FEDC	Abstract	C00823 MNYCP 02	Perturbation and Sensitivity Code for Assembly Homogenized Multi-group Transport Problems
REFREP	Abstract	C00570 D8810 00	A Near-Field Model For A Spent Fuel Repository.
SAM-CEP	Abstract	C00192 C6600 00	Monte Carlo Code System Correlated to the Simultaneous Solution of Multiple, Perturbed, Time-Dependent Neutron Transport Problems in Complex Three-Dimensional Geometry.
SARA 4.16	Abstract	P00484 IBMPC 00	System Analysis and Risk Assessment System.
SENSIT	Abstract	C00405 C7600 00	One-Dimensional, Multigroup Cross Section and Design Sensitivity and Uncertainty Analysis Code System - Generalized Perturbation Theory.
SFHA USSO	Abstract	P00413 IBMPC 00	Code System for Spent Fuel Heating Analysis.
SPHINX	Abstract	P00129 C7600 00	A One-Dimensional Diffusion and Transport Nuclear Cross Section Processing Code System.
SPHINX	Abstract	P00129 I0360 00	A One-Dimensional Diffusion and Transport Nuclear Cross Section Processing Code System.
STRADE	Abstract	P00252 I3081 00	Stratified Random Design.
SUSD	Abstract	C00501 HM150 00	Cross Section Sensitivity and Uncertainty Analysis Including Secondary Neutron Energy and Angular Distributions.
SUSD	Abstract	C00501 I3090 00	Cross Section Sensitivity and Uncertainty Analysis Including Secondary Neutron Energy and Angular Distributions.
SUSD3D	Abstract	C00695 MNYCP 01	Multi-Dimensional, Discrete-Ordinates Based Cross Section Sensitivity and Uncertainty Analysis Code System.
SWANLAKE	Abstract	C00204 C6600 00	Cross Section Sensitivity Analysis Code System for One-Dimensional Discrete Ordinates Calculations.
SWANLAKE	Abstract	C00204 I3033 00	Cross Section Sensitivity Analysis Code System for One-Dimensional Discrete Ordinates Calculations.
TAM3	Abstract	P00308 IBMPC 00	Demonstrates Monte Carlo Sensitivity and Uncertainty Analysis.
TEMAC	Abstract	P00468 D0VAX 00	Top Event Matrix Analysis Code System.
UMG 3.3	Abstract	P00529 PC586 00	Unfolding with Maxed and Gravel.
VENTURE-PC	Abstract	C00654 PC586 02	A Reactor Analysis Code System.
XSUN-2013	Abstract	C00825 PCX86 00	Windows interface environment for transport and sensitivity-uncertainty software TRANSX-2, PARTISN and SUSD3D
ZOTT99	Abstract	P00272 ALLCP 02	Zero-in On The Truth; Evaluation of Correlated Data Using Partitioned Least Squares.

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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.