Show simple item record

dc.contributor.advisorRagusa, Jean C.
dc.creatorZhang, Yunhuang
dc.date.accessioned2011-02-22T22:23:59Z
dc.date.accessioned2011-02-22T23:46:59Z
dc.date.available2011-02-22T22:23:59Z
dc.date.available2011-02-22T23:46:59Z
dc.date.created2009-12
dc.date.issued2011-02-22
dc.date.submittedDecember 2009
dc.identifier.urihttps://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7470
dc.description.abstractThe accumulation of spent nuclear fuel may be hindering the expansion of nuclear electricity production. However, the reprocessing and recycling of spent fuel may reduce its volume and environmental burden. Although fast spectrum reactors are the preferred modality for transuranic element transmutation, such fast spectrum systems are in very short supply. It is therefore legitimate to investigate the recycling potential of thermal spectrum systems, which constitute the overwhelming majority of nuclear power plants worldwide. To do so efficiently, several new fuel assembly designs are proposed in this Thesis: these include (1) Mixed Oxide Fuel (MOX), (2) MOX fuel with Americium coating, (3) Inert-Matrix Fuel (IMF) with UOX as inner zone, and (4) IMF with MOX as inner zone. All these designs are investigated in a multi-recycling strategy, whereby the spent fuel from a given generation is re-used for the next generation. The accumulation of spent nuclear fuel may be hindering the expansion of nuclear electricity production. However, the reprocessing and recycling of spent fuel may reduce its volume and environmental burden. Although fast spectrum reactors are the preferred modality for transuranic element transmutation, such fast spectrum systems are in very short supply. It is therefore legitimate to investigate the recycling potential of thermal spectrum systems, which constitute the overwhelming majority of nuclear power plants worldwide. To do so efficiently, several new fuel assembly designs are proposed in this Thesis: these include (1) Mixed Oxide Fuel (MOX), (2) MOX fuel with Americium coating, (3) Inert-Matrix Fuel (IMF) with UOX as inner zone, and (4) IMF with MOX as inner zone. All these designs are investigated in a multi-recycling strategy, whereby the spent fuel from a given generation is re-used for the next generation.en
dc.format.mimetypeapplication/pdf
dc.language.isoen_US
dc.subjectTransuranics Transmutationen
dc.subjectNuclear Fuel Multi-Recyclingen
dc.subjectAdvanced MOXen
dc.subjectIMFen
dc.subjectFuel Assemblyen
dc.subjectLong-term Radiotoxicityen
dc.subjectLong-term Decay Heaten
dc.subjectAmericium Coatingen
dc.titleTransmutation of Transuranic Elements in Advanced MOX and IMF Fuel Assemblies Utilizing Multi-recycling Strategiesen
dc.typeBooken
dc.typeThesisen
thesis.degree.departmentNuclear Engineeringen
thesis.degree.disciplineNuclear Engineeringen
thesis.degree.grantorTexas A&M Universityen
thesis.degree.nameMaster of Scienceen
thesis.degree.levelMastersen
dc.contributor.committeeMemberTsvetkov, Pavel V.
dc.contributor.committeeMemberDaripa, Prabir
dc.type.genreElectronic Thesisen
dc.type.materialtexten


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record