Published January 1, 2008 | Version v1
Miscellaneous

SCALE-6 Sensitivity/Uncertainty Methods and Covariance Data

  • 1. Oak Ridge National Laboratory, TN (United States)

Description

Computational methods and data used for sensitivity and uncertainty analysis within the SCALE nuclear analysis code system are presented. The methodology used to calculate sensitivity coefficients and similarity coefficients and to perform nuclear data adjustment is discussed. A description is provided of the SCALE-6 covariance library based on ENDF/B-VII and other nuclear data evaluations, supplemented by 'low-fidelity' approximate covariances. SCALE (Standardized Computer Analyses for Licensing Evaluation) is a modular code system developed by Oak Ridge National Laboratory (ORNL) to perform calculations for criticality safety, reactor physics, and radiation shielding applications. SCALE calculations typically use sequences that execute a predefined series of executable modules to compute particle fluxes and responses like the critical multiplication factor. SCALE also includes modules for sensitivity and uncertainty (S/U) analysis of calculated responses. The S/U codes in SCALE are collectively referred to as TSUNAMI (Tools for Sensitivity and UNcertainty Analysis Methodology Implementation). SCALE-6-scheduled for release in 2008-contains significant new capabilities, including important enhancements in S/U methods and data. The main functions of TSUNAMI are to (a) compute nuclear data sensitivity coefficients and response uncertainties, (b) establish similarity between benchmark experiments and design applications, and (c) reduce uncertainty in calculated responses by consolidating integral benchmark experiments. TSUNAMI includes easy-to-use graphical user interfaces for defining problem input and viewing three-dimensional (3D) geometries, as well as an integrated plotting package.

Availability note (English)

Available from Oak Ridge National Laboratory, TN (US)

Additional details

Publishing Information

Imprint Pagination
5 p.

Conference

Title
Workshop on Neutron Cross Section Covariances
Dates
24-27 Jun 2008
Place
Port Jefferson, NY (United States)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
43008953
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BENCHMARKS; COMPUTERS; CRITICALITY; CROSS SECTIONS; DESIGN; EVALUATION; IMPLEMENTATION; LICENSING; MULTIPLICATION FACTORS; NEUTRONS; ORNL; RADIATIONS; REACTOR PHYSICS; SAFETY; SENSITIVITY; SHIELDING
Descriptors DEC
BARYONS; DIMENSIONLESS NUMBERS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; NATIONAL ORGANIZATIONS; NUCLEONS; PHYSICS; US AEC; US DOE; US ERDA; US ORGANIZATIONS

Optional Information

Contract/Grant/Project number
AC05-00OR22725
Notes
pages 2786-2800
Funding organization
US Department of Energy (United States)