The role of integral data in neutron cross-section evaluation

A. Pazy, G. Rakavy, I. Reiss, J.J. Wagschal, A. Ya'ari

Research output: Contribution to journalArticlepeer-review


The authors give an up-to-date, detailed, and rigorous presentation of the generalized least-squares procedure developed to improve neutron cross-section evaluations, based on direct cross-section measurements by means of integral data. Both discrete and continuous (energy dependent) integral quantities are considered. Explicit expressions are derived for the best estimates of the cross sections in a continuous form, as well as in the multigroup approximation.
Original languageEnglish
Pages (from-to)280 - 95
JournalNuclear Science and Engineering
Issue number3
StatePublished - Nov 1974

Bibliographical note

neutron cross section evaluation;generalised least squares procedure;multigroup approximation;integral data;


  • least squares approximations
  • neutron transport theory
  • nuclear reactor theory


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