Published November 1989 | Version v1
Journal article

Impact of ENDF/B-VI [Evaluated Nuclear Data File] on thermal reactor benchmark calculations

  • 1. Louisiana State Univ., Baton Rouge (USA)
  • 2. Oak Ridge National Laboratory, TN (USA)

Description

The ENDF/B-VI [Evaluated Nuclear Data File] data evaluations reflect several major changes relative to version V data that will be of interest in thermal reactor analysis. Some of the important changes in the 235U, 239Pu, and 238U data are summarized. It can be seen that significant modifications have been made in the 235U and 239Pu thermal data. Also, completely new resonance evaluations based on the Reich-Moore formalism have been performed for 235U, 239Pu, and 238U, and the number of resolved resonances included in the evaluations has increased dramatically. To assess the merit of these modifications, it is first necessary to review the performance of ENDF/B-V in thermal reactor analysis and then to project the estimated impact of ENDF/B-VI on the version V results

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
60
Series
Trans. Am. Nucl. Soc.
Journal Page Range
619-620
ISSN
0003-018X
CODEN
TANSA

Conference

Title
Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
Dates
26-30 Nov 1989.
Place
San Francisco, CA (USA).

Optional Information

Secondary number(s)
CONF-891103--.