Application of the Monte Carlo transport code MORSE to the calculation of pulsed neutron experiments

Abstract

An accurate calculation tool is essential for the assessment of nuclear data by the pulsed neutron technique. The Monte Carlo transport code MORSE is such a tool and its application to the calculation of pulsed neutron experiments is presented. Modifications to the code and a set of ancillary programs to enable the direct comparison of calculation with experiment are described. The time profile of the pulsed neutron source is treated in a manner which allows more efficient use of the code. However, as a consequence some parameters, such as detector responses at different times, are no longer uncorrelated. Error analysis which takes proper account of these correlations is presented.