Title:
Assessing internal contamination levels for fission product inhalation using a portal monitor

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dc.contributor.advisor Hertel, Nolan E.
dc.contributor.author Freibert, Emily Jane en_US
dc.contributor.committeeMember Ansari, Armin
dc.contributor.committeeMember Wang, C-K Chris
dc.contributor.department Mechanical Engineering en_US
dc.date.accessioned 2011-03-04T20:20:57Z
dc.date.available 2011-03-04T20:20:57Z
dc.date.issued 2010-11-18 en_US
dc.description.abstract In the event of a nuclear power plant accident, fission products could be released into the atmosphere potentially affecting the health of local citizens. In order to triage the possibly large number of people impacted, a detection device is needed that can acquire data quickly and that is sensitive to internal contamination. The portal monitor TPM-903B was investigated for use in the event of a fission product release. A list of fission products released from a Pressurized Water Reactor (PWR) was generated and separated into two groups--Group 1 (gamma- and beta-emitting fission products) and Group 2 (strictly beta-emitting fission products.) Group one fission products were used in the previously validated Monte Carlo N-Particle Transport Code (MCNP) model of the portal monitor. Two MIRD anthropomorphic phantom types were implemented in the MCNP model--the Adipose Male and Child phantoms. Dose and Risk Calculation software (DCAL) provided inhalation biokinetic data that were applied to the output of the MCNP modeling to determine the radionuclide concentrations in each organ as a function of time. For each phantom type, these data were used to determine the total body counts associated with each individual gamma-emitting fission product. Corresponding adult and child dose coefficients were implemented to determine the total body counts per 250 mSv. A weighted sum of all of the isotopes involved was performed. The ratio of dose associated with gamma-emitting fission products to the total of all fission products was determined based on corresponding dose coefficients and relative abundance. This ratio was used to project the total body counts corresponding to 250mSv for the entire fission product release inhalation--including all types of radiation. The developed procedure sheets will be used by first response personnel in the event of a fission product release. en_US
dc.description.degree M.S. en_US
dc.identifier.uri http://hdl.handle.net/1853/37184
dc.publisher Georgia Institute of Technology en_US
dc.subject Internal contamination en_US
dc.subject Fission products en_US
dc.subject Inhalation en_US
dc.subject Accident scenario en_US
dc.subject TPM 903B en_US
dc.subject Portal monitor en_US
dc.subject.lcsh Nuclear power plants Accidents
dc.subject.lcsh Fission products
dc.subject.lcsh Radioactive substances Detection Equipment and supplies
dc.title Assessing internal contamination levels for fission product inhalation using a portal monitor 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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