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Title: Application of the Monte Carlo transport code MORSE to the calculation of pulsed neutron experiments.
Authors: Rainbow, MT
Issue Date: Mar-1978
Publisher: Australian Nuclear Science and Technology Organisation
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.
ISBN: 0642596646
Appears in Collections:Scientific and Technical Reports

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