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: PERTURBATION THEORY
Package NameAbstractRSICC TapelistTitle
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
GENP-2AbstractC00575 ALLMF 00Generalized Perturbation Theory Code System.
JDL-IMPORTANCEAbstractM00005 MNYCP 00Adjoint Function: Physical Basis of Variational & Perturbation Theory in Transport & Diffusion Problems.
MTR_PC 2.6AbstractC00674 PC386 00Modular Code System for Neutronics, Thermalhydraulics and Shielding Calculations.
PERSENT 11.2892
FEDC		AbstractC00823 MNYCP 02Perturbation and Sensitivity Code for Assembly Homogenized Multi-group Transport Problems
SENSITAbstractC00405 C7600 00One-Dimensional, Multigroup Cross Section and Design Sensitivity and Uncertainty Analysis Code System - Generalized Perturbation Theory.
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.
TP1AbstractC00465 I3033 00A Computer Code System for the Calculation of Reactivity and Kinetic Parameters by One-Dimensional Neutron Transport Perturbation Theory.
TP2AbstractC00470 I3033 00A Computer Code System for the Calculation of Reactivity and Kinetic Parameters by One-Dimensional Neutron Transport Perturbation Theory.
TPTRIAAbstractC00550 I3083 00A Computer Program for the Reactivity and Kinetic Parameters for Two-Dimensional Triangular Geometry by Transport Perturbation Theory.
VENTURE-PCAbstractC00654 PC586 02A Reactor Analysis Code System.
123ABCDEFGHIJKLMNOPQRSTUVWXYZ
FAQ | ORNL Home | DOE | Site Map | Security Notice
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.