ORACLE: an adjusted cross-section and covariance library for fast-reactor analysis

Y. Yeivin, J.H. Marable, C.R. Weisbin, J.J. Wagschal

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review


Benchmark integral-experiment values from six fast critical-reactor assemblies and two standard neutron fields are combined with corresponding calculations using group cross sections based on ENDF/B-V in a least-squares data adjustment using evaluated covariances from ENDF/B-V and supporting covariance evaluations. The purpose is to produce an adjusted cross-section and covariance library which is based on well-documented data and methods and which is suitable for fast-reactor design. By use of such a library, data- and methods-related biases of calculated performance parameters should be reduced and uncertainties of the calculated values minimized. Consistency of the extensive data base is analyzed using the chi-square test. This adjusted library ORACLE will be available shortly. Feedback from designers, evaluators, experimentalists, and analysts is solicited.
Original languageEnglish
Title of host publicationProceedings of the Conference, 1980 Advances in Reactor Physics and Shielding
Subtitle of host publicationSeptember 14-17, 1980, Sun Valley, Idaho
Place of PublicationLaGrange Park, IL, USA
PublisherAmerican Nuclear Society
Pages705 - 19
Number of pages14
StatePublished - 1980

Bibliographical note

ORACLE;adjusted cross-section;covariance library;fast-reactor analysis;critical-reactor assemblies;standard neutron fields;group cross sections;ENDF/B-V;


  • fission reactor core control and monitoring
  • fission reactor theory and design


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