The determination of the error in monitoring the neutron flux and fluence in a nuclear reactor

Neutron flux and fluence monitoring during irradiation experiments is based on the knowledge of the neutron spectrum in the irradiation facility and on the cross section of the detector employed. The accuracy of monitoring is predominantly determined by the accuracy of these quantities and by the experimental technique. The relations used in the evaluation of the monitored quantity are listed in integral form and in a group approximation. Supposing that complete covariance matrices of the neutron spectrum and of the neutron cross sections are available, the variances of the monitored quantities are derived. The solutions of some problems tied with the transitions between various group formats are also considered. (author). 1 tab., 4 refs