Online Catalog
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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 NameAbstractRSICC TapelistTitle
ABLEIT-TRANSAbstractP00247 C0175 00Error Propagation Analysis for Burnup Calculation.
ARC 11.2892
FEDC		AbstractC00824 MNYCP 02Code System for Analysis of Nuclear Reactors.
BOLD VENTURE IVAbstractC00459 I3033 00A Reactor Analysis Code System.
ERANOS 2.0
OECD		AbstractC00745 MNYWS 00Modular Code and Data System for Fast Reactor Neutronics Analyses
ERRORJAbstractP00526 MNYCP 03Multigroup Covariance Matrices Generation from ENDF/B-6 Format.
FORSENAbstractP00170 I0360 00A Multigroup Processing Code for Use with Sensitivity Profiles to Assess the Effect of Cross Section Changes.
FORSSAbstractC00334 C0000 00A Sensitivity and Uncertainty Analysis Code System.
FORSSAbstractC00334 I0360 00A Sensitivity and Uncertainty Analysis Code System.
GANDR/SEMOVEAbstractC00765 PCX86 00Program for Calculating Derivatives of Processed Multigroup Nuclear Data by Discrete Differences.
GRESS 3.0AbstractP00231 MFMWS 02Gradient Enhanced Software System.
LEPRICONAbstractP00277 I3033 01PWR Pressure Vessel Surveillance Dosimetry Analysis System.
LEPRICONAbstractP00277 IRISC 00PWR Pressure Vessel Surveillance Dosimetry Analysis System.
NEUPACAbstractP00177 FM200 00Neutron Unfolding Code System for Calculating Neutron Flux Spectra from Activation Data of Dosimeter Foils.
PCC/SRCAbstractP00456 D0VAX 00Code System to Calculate Correlation & Regression Coefficients.
PERSENT 11.2892
FEDC		AbstractC00823 MNYCP 02Perturbation and Sensitivity Code for Assembly Homogenized Multi-group Transport Problems
REFREPAbstractC00570 D8810 00A Near-Field Model For A Spent Fuel Repository.
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.
SARA 4.16AbstractP00484 IBMPC 00System Analysis and Risk Assessment System.
SENSITAbstractC00405 C7600 00One-Dimensional, Multigroup Cross Section and Design Sensitivity and Uncertainty Analysis Code System - Generalized Perturbation Theory.
SFHA
USSO		AbstractP00413 IBMPC 00Code System for Spent Fuel Heating Analysis.
SPHINXAbstractP00129 C7600 00A One-Dimensional Diffusion and Transport Nuclear Cross Section Processing Code System.
SPHINXAbstractP00129 I0360 00A One-Dimensional Diffusion and Transport Nuclear Cross Section Processing Code System.
STRADEAbstractP00252 I3081 00Stratified Random Design.
SUSDAbstractC00501 HM150 00Cross Section Sensitivity and Uncertainty Analysis Including Secondary Neutron Energy and Angular Distributions.
SUSDAbstractC00501 I3090 00Cross Section Sensitivity and Uncertainty Analysis Including Secondary Neutron Energy and Angular Distributions.
SUSD3DAbstractC00695 MNYCP 01Multi-Dimensional, Discrete-Ordinates Based Cross Section Sensitivity and Uncertainty Analysis Code System.
SWANLAKEAbstractC00204 C6600 00Cross Section Sensitivity Analysis Code System for One-Dimensional Discrete Ordinates Calculations.
SWANLAKEAbstractC00204 I3033 00Cross Section Sensitivity Analysis Code System for One-Dimensional Discrete Ordinates Calculations.
TAM3AbstractP00308 IBMPC 00Demonstrates Monte Carlo Sensitivity and Uncertainty Analysis.
TEMACAbstractP00468 D0VAX 00Top Event Matrix Analysis Code System.
UMG 3.3AbstractP00529 PC586 00Unfolding with Maxed and Gravel.
VENTURE-PCAbstractC00654 PC586 02A Reactor Analysis Code System.
XSUN-2013AbstractC00825 PCX86 00Windows interface environment for transport and sensitivity-uncertainty software TRANSX-2, PARTISN and SUSD3D
ZOTT99AbstractP00272 ALLCP 02Zero-in On The Truth; Evaluation of Correlated Data Using Partitioned Least Squares.
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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.