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dc.contributor.advisorReece, W. Danen_US
dc.creatorChen, Yongen_US
dc.date.accessioned2010-01-14T23:57:41Zen_US
dc.date.accessioned2010-01-16T00:19:55Z
dc.date.available2010-01-14T23:57:41Zen_US
dc.date.available2010-01-16T00:19:55Z
dc.date.created2006-12en_US
dc.date.issued2009-05-15en_US
dc.identifier.urihttp://hdl.handle.net/1969.1/ETD-TAMU-1134
dc.description.abstractThe delayed neutron emission rates of U-235 and Pu-239 samples were measured accurately from a thermal fission reaction. A Monte Carlo calculation using the Geant4 code was used to demonstrate the neutron energy independence of the detector used in the counting station. A set of highly purified actinide samples (U-235 and Pu-239) was irradiated in these experiments by using the Texas A&M University Nuclear Science Center Reactor. A fast pneumatic transfer system, an integrated computer control system, and a graphite-moderated counting system were constructed to perform all these experiments. The calculated values for the five-group U-235 delayed neutron parameters and the six-group Pu-239 delayed neutron parameters were compared with the values recommended by Keepin et al. (1957) and Waldo et al. (1981). These new values differ slightly from literature values. The graphite-moderated counting station and the computerized pneumatic system are now operational for further delayed neutron measurement.en_US
dc.format.mediumelectronicen_US
dc.format.mimetypeapplication/pdfen_US
dc.language.isoen_USen_US
dc.subjectdelayed neutronen_US
dc.subjectemission rateen_US
dc.titleDelayed neutron emission measurements for U-235 and Pu-239en_US
dc.typeThesisen
thesis.degree.departmentNuclear Engineeringen_US
thesis.degree.disciplineHealth Physicsen_US
thesis.degree.grantorTexas A&M Universityen_US
thesis.degree.nameMaster of Scienceen_US
thesis.degree.levelMastersen_US
dc.contributor.committeeMemberCharlton, William. Een_US
dc.contributor.committeeMemberWatson, Rand. Len_US
dc.type.genrethesisen_US
dc.type.materialtexten_US
dc.format.digitalOriginborn digitalen_US


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