Title:
Evaluation of internal contamination levels after a radiological dispersal device using portal monitors

dc.contributor.advisor Hertel, Nolan E.
dc.contributor.author Palmer, Randahl Christelle en_US
dc.contributor.committeeMember Ansari, Armin
dc.contributor.committeeMember Wang, C-K Chris
dc.contributor.department Nuclear and Radiological Engineering en_US
dc.date.accessioned 2011-03-04T20:13:47Z
dc.date.available 2011-03-04T20:13:47Z
dc.date.issued 2010-08-24 en_US
dc.description.abstract In the event of a radioactive dispersal device (RDD), the assessment of the internal contamination level of victims is necessary to determine if immediate medical follow-up is necessary. Thermo Scientific's TPM-903B Portal Monitor was investigated to determine if it is a suitable first cut screening tool for internal contamination assessment of victims. A portal monitor was chosen for this study because they are readily accessible, transportable, easy to assemble, and provide whole body count rates due to the detector size. The TPM-903B was modeled in Monte Carlo N-Particles Transport Code Version 5 (MCNP). This computational model was validated against the portal monitor's response to a series of measurements made with four point sources in a polymethyl methacrylate (PMMA) slab box. Using the validated MCNP5 model and models of the MIRD male and female anthropomorphic phantoms, the response of the portal monitor was simulated for the inhalation and ingestion radionuclides from an RDD. Six representative phantoms were considered: Reference Male, Reference Female, Adipose Male, Adipose Female, Post-Menopausal Adipose Female, and 10-Year-Old Child. The biokinetics via Dose and Risk Calculation Software (DCAL) was implemented using both the inhalation and ingestion pathways to determine the radionuclide concentrations in the organs of the body which were then used to determine the count rate of the portal monitor as a function of time. Dose coefficients were employed to determine the count rate of the detector associated with specific dose limits. These count rates were then compiled into procedure sheets to be used by first responders during the triaging of victims following an RDD. en_US
dc.description.degree M.S. en_US
dc.identifier.uri http://hdl.handle.net/1853/37115
dc.publisher Georgia Institute of Technology en_US
dc.subject Portal monitors en_US
dc.subject Internal contamination en_US
dc.subject Dose en_US
dc.subject RDD en_US
dc.subject.lcsh Dirty bombs
dc.subject.lcsh Radioactive substances Detection
dc.subject.lcsh Radiation dosimetry
dc.subject.lcsh Radiation victims
dc.subject.lcsh Emergency management
dc.title Evaluation of internal contamination levels after a radiological dispersal device using portal monitors 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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