Published 1994 | Version v1
Book

Influence of neutron data uncertainties on accuracy of prediction of advanced reactor characteristics

  • 1. Institute of Physics and Power Engineering, Obninsk (Russian Federation)

Description

Different sources of uncertainties caused by different nuclear cross sections are analyzed for a few types of advanced reactors: the BN-800 FBR core, advanced FBR core with Pb-Bi coolant, modular FBR core with U-Pu and U-Th fuel, HCLWR lattices. Estimations have been made with help of the INDECS System of Codes and Archives. Constructed convariance matrices of uncertainties of the ABB-90 group constants were used for estimation of accuracy of prediction of the most important neutronics characteristics of advanced reactor cores

Additional details

Publishing Information

Publisher
American Nuclear Society, Inc.
Imprint Place
La Grange Park, IL (United States)
Imprint Title
Proceedings of the international conference nuclear data for science and technology. Volume 2
Imprint Pagination
571 p.
Journal Page Range
p. 993-999.

Conference

Title
nuclear data for the twenty-first century.
Acronym
International conference on nuclear data for science and technology
Dates
9-13 May 1994.
Place
Gatlinburg, TN (United States).