Abstract
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 language | English |
|---|---|
| Pages (from-to) | 280 - 95 |
| Journal | Nuclear Science and Engineering |
| Volume | 55 |
| Issue number | 3 |
| State | Published - Nov 1974 |
Bibliographical note
neutron cross section evaluation;generalised least squares procedure;multigroup approximation;integral data;Keywords
- least squares approximations
- neutron transport theory
- nuclear reactor theory