skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Covariance matrices for nuclear cross sections derived from nuclear model calculations.

Technical Report ·
DOI:https://doi.org/10.2172/838257· OSTI ID:838257

The growing need for covariance information to accompany the evaluated cross section data libraries utilized in contemporary nuclear applications is spurring the development of new methods to provide this information. Many of the current general purpose libraries of evaluated nuclear data used in applications are derived either almost entirely from nuclear model calculations or from nuclear model calculations benchmarked by available experimental data. Consequently, a consistent method for generating covariance information under these circumstances is required. This report discusses a new approach to producing covariance matrices for cross sections calculated using nuclear models. The present method involves establishing uncertainty information for the underlying parameters of nuclear models used in the calculations and then propagating these uncertainties through to the derived cross sections and related nuclear quantities by means of a Monte Carlo technique rather than the more conventional matrix error propagation approach used in some alternative methods. The formalism to be used in such analyses is discussed in this report along with various issues and caveats that need to be considered in order to proceed with a practical implementation of the methodology.

Research Organization:
Argonne National Lab., Argonne, IL (US)
Sponsoring Organization:
US Department of Energy (US)
DOE Contract Number:
W-31-109-ENG-38
OSTI ID:
838257
Report Number(s):
ANL/NDM-159; TRN: US0501296
Resource Relation:
Other Information: PBD: 10 Jan 2005
Country of Publication:
United States
Language:
English

Similar Records

A New Approach for Nuclear Data Covariance and Sensitivity Generation
Journal Article · Tue May 24 00:00:00 EDT 2005 · AIP Conference Proceedings · OSTI ID:838257

Covariance data for ENDF/B-VI (Evaluated Nuclear Data File)
Conference · Wed Nov 01 00:00:00 EST 1989 · Transactions of the American Nuclear Society; (United States) · OSTI ID:838257

Inventory Uncertainty Quantification using TENDL Covariance Data in Fispact-II
Journal Article · Thu Jan 15 00:00:00 EST 2015 · Nuclear Data Sheets · OSTI ID:838257