Title:
A rapid, reliable methodology for radionuclide characterization of wet or dry stored used nuclear fuel via the application of algorithm-enhanced scintillator survey spectra

dc.contributor.advisor Deo, Chaitanya S.
dc.contributor.author Paul, Jessica Nicole
dc.contributor.committeeMember Rahnema, Farzad
dc.contributor.committeeMember Yi, Ce
dc.contributor.committeeMember Pope, Chad
dc.contributor.committeeMember Sjoden, Glenn E.
dc.contributor.department Mechanical Engineering
dc.date.accessioned 2015-09-21T14:22:03Z
dc.date.available 2015-09-21T14:22:03Z
dc.date.created 2015-08
dc.date.issued 2015-05-07
dc.date.submitted August 2015
dc.date.updated 2015-09-21T14:22:03Z
dc.description.abstract The growing concern regarding regulation and accountability of plutonium and SNM produced in commercial and research nuclear reactor fuel has driven the need for new spent nuclear fuel characterization methods to enable quantification and qualification of radioisotopes contained in used fuel in a reliable, quick, and inexpensive manner, with little to no impact on normal reactor operating procedures. This research aims to meet these objectives by employing advanced computational radiation transport methods incorporated into an algorithm to post process scintillator detector data gathered from used nuclear fuel in a spent fuel pool or in air. An existing, novel post processing algorithm, SmartID, has been updated to extract and identify unique photopeaks represented in the underwater environment for pool cooled used fuel. The resulting spectral data will be post-processed using an updated SmartID algorithm folded with deterministic adjoint results to render both qualitative and quantitative fuel content and irradiation estimates. This work has much significance to the nuclear power industry, safeguards, and forensics communities, since it yields this information at room temperature for a relatively low cost.
dc.description.degree Ph.D.
dc.format.mimetype application/pdf
dc.identifier.uri http://hdl.handle.net/1853/53833
dc.language.iso en_US
dc.publisher Georgia Institute of Technology
dc.subject SmartID
dc.subject Adjoint
dc.subject Transport
dc.subject NaI
dc.subject Detector response
dc.title A rapid, reliable methodology for radionuclide characterization of wet or dry stored used nuclear fuel via the application of algorithm-enhanced scintillator survey spectra
dc.type Text
dc.type.genre Dissertation
dspace.entity.type Publication
local.contributor.advisor Deo, Chaitanya S.
local.contributor.corporatename George W. Woodruff School of Mechanical Engineering
local.contributor.corporatename College of Engineering
relation.isAdvisorOfPublication e70a4cb9-5a0d-4c70-8cab-031b27668247
relation.isOrgUnitOfPublication c01ff908-c25f-439b-bf10-a074ed886bb7
relation.isOrgUnitOfPublication 7c022d60-21d5-497c-b552-95e489a06569
thesis.degree.level Doctoral
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