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

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dc.contributor.authorRainbow, MTen_AU
dc.date.accessioned2007-11-22T04:27:37Zen_AU
dc.date.accessioned2010-04-30T04:38:31Zen_AU
dc.date.available2007-11-22T04:27:37Zen_AU
dc.date.available2010-04-30T04:38:31Zen_AU
dc.date.issued1978-03en_AU
dc.description.abstractAn 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.en_AU
dc.identifier.citationRainbow, 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.en_AU
dc.identifier.govdoc684en_AU
dc.identifier.isbn0642596646en_AU
dc.identifier.otherAAEC-E-461en_AU
dc.identifier.placeofpublicationLucas Heights, New South Walesen_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/674en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Atomic Energy Commissionen_AU
dc.subjectNeutron transporten_AU
dc.subjectPulsed neutron techniquesen_AU
dc.subjectComputer calculationsen_AU
dc.subjectM codesen_AU
dc.subjectMonte Carlo Methoden_AU
dc.subjectNeutron beamsen_AU
dc.subjectNeutron transport theoryen_AU
dc.titleApplication of the Monte Carlo transport code MORSE to the calculation of pulsed neutron experimentsen_AU
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