Title:
Uranium-232 Beryllide Neutron Source

dc.contributor.advisor Hertel, Nolan E.
dc.contributor.author Bechtel, Ryan Daniel en_US
dc.contributor.committeeMember Tedder, Daniel
dc.contributor.committeeMember Wang, C-K Chris
dc.contributor.department Mechanical Engineering en_US
dc.date.accessioned 2007-05-25T17:49:24Z
dc.date.available 2007-05-25T17:49:24Z
dc.date.issued 2006-10-23 en_US
dc.description.abstract A [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.description.degree M.S. en_US
dc.identifier.uri http://hdl.handle.net/1853/14650
dc.publisher Georgia Institute of Technology en_US
dc.subject UBe13 en_US
dc.subject Neutron production en_US
dc.subject Dirty uranium en_US
dc.subject (Alpha n) en_US
dc.subject (A n) en_US
dc.subject Uranium-232 en_US
dc.title Uranium-232 Beryllide Neutron Source en_US
dc.type Text
dc.type.genre Thesis
dspace.entity.type Publication
local.contributor.advisor Hertel, Nolan E.
local.contributor.corporatename George W. Woodruff School of Mechanical Engineering
local.contributor.corporatename College of Engineering
relation.isAdvisorOfPublication 26003284-0ae0-4887-a127-917eb8923925
relation.isOrgUnitOfPublication c01ff908-c25f-439b-bf10-a074ed886bb7
relation.isOrgUnitOfPublication 7c022d60-21d5-497c-b552-95e489a06569
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