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dc.contributor.advisorPoston, John W, SR.
dc.creatorCoker, Audra Lee
dc.date.accessioned2007-09-17T19:34:41Z
dc.date.available2007-09-17T19:34:41Z
dc.date.created2003-05
dc.date.issued2007-09-17
dc.identifier.urihttps://hdl.handle.net/1969.1/5836
dc.description.abstractThe objective of this project was to compare two different methods of calculating dose through lead-shielded walls in the PET/CT suite at Scott & White Hospital in Temple, Texas. The ultimate goal was to see which of the two methods agreed with the actual physical measurements. Minimizing shielding needed in future suite designs would result in a possible reduction of structural as well as financial burden. Formulas and attenuation coefficients following the basic January 2006 AAPM guidelines were used to calculate unattenuated radiation through existing lead walls. The computer code MCNPX was used to simulate the leaded walls of the PET/CT suite and provide another set of results. These two sets of results were compared to doses gathered from OSL badges placed around the suite for a period of two months. For this type of problem, MCNPX proved to provide results that were inconsistent and unreliable. It was concluded that the traditional computational methods are the most reliable for designing shielding in a PET/CT suite.en
dc.format.extent521021 bytesen
dc.format.mediumelectronicen
dc.format.mimetypeapplication/pdf
dc.language.isoen_US
dc.publisherTexas A&M University
dc.subjectshieldingen
dc.subjectPETen
dc.titlePET/CT shielding design comparisonsen
dc.typeBooken
dc.typeThesisen
thesis.degree.departmentNuclear Engineeringen
thesis.degree.disciplineHealth Physicsen
thesis.degree.grantorTexas A&M Universityen
thesis.degree.nameMaster of Scienceen
thesis.degree.levelMastersen
dc.contributor.committeeMemberBoyer, Art
dc.contributor.committeeMemberFord, John R.
dc.contributor.committeeMemberWalker, Michael
dc.type.genreElectronic Thesisen
dc.type.materialtexten
dc.format.digitalOriginborn digitalen


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