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dc.contributor.authorBechtel, Ryan Danielen_US
dc.date.accessioned2007-05-25T17:49:24Z
dc.date.available2007-05-25T17:49:24Z
dc.date.issued2006-10-23en_US
dc.identifier.urihttp://hdl.handle.net/1853/14650
dc.description.abstractA [U-232]UBe13 neutron source was designed and modeled and the fluence and flux distributions were calculated. The [U-232]U decay chain emits six high energy alpha particles in quick succession and is ideal for use in a beryllium (a,n) neutron source. [U-232]U is an undesirable byproduct in the production of [U-233]U in the thorium fuel cycle; its concentrations can vary from 5-3000 ppm in bred [U-233]U. A 1.1018-cm diameter by 1.1018-cm tall cylinder of [U-233]UBe13 with 300ppm U-232 at 0.74 GBq (20 mCi) was modeled and found to have a peak yield of 3.5*105 n/s after 10.17 years. At this peak yield, the [U-232]UBe13 source has better neutron production efficiency per initial alpha emission activity than other beryllide neutron sources.en_US
dc.publisherGeorgia Institute of Technologyen_US
dc.subjectUBe13en_US
dc.subjectNeutron productionen_US
dc.subjectDirty uraniumen_US
dc.subject(Alpha n)en_US
dc.subject(A n)en_US
dc.subjectUranium-232en_US
dc.titleUranium-232 Beryllide Neutron Sourceen_US
dc.typeThesisen_US
dc.description.degreeM.S.en_US
dc.contributor.departmentMechanical Engineeringen_US
dc.description.advisorCommittee Chair: Hertel, Nolan; Committee Member: Tedder, Daniel; Committee Member: Wang, Chrisen_US


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