Application of the Monte Carlo transport code MORSE to the calculation of pulsed neutron experiments
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Date
1978-03
Authors
Journal Title
Journal ISSN
Volume Title
Publisher
Australian Atomic Energy Commission
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.
Description
Keywords
Neutron transport, Pulsed neutron techniques, Computer calculations, M codes, Monte Carlo Method, Neutron beams, Neutron transport theory
Citation
Rainbow, M. T. (1978). Application of the Monte Carlo transport code MORSE to the calculation of pulsed neutron experiments (AAEC/E461). Lucas Heights, NSW: Australian Atomic Energy Commission.