Published January 1, 2012 | Version v1
Journal article

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

  • 1. Georgia Institute of Technology, Atlanta, GA (United States)
  • 2. Centers for Disease Control and Prevention, Atlanta, GA (United States)
  • 3. Oak Ridge National Laboratory, Oak Ridge, TN (United States)

Description

Following a radioactive dispersal device (RDD) incident, it may be necessary to evaluate the internal contamination levels of a large number of potentially affected individuals to determine if immediate medical follow-up is necessary. Since the current laboratory capacity to screen for internal contamination is limited, rapid field screening methods can be useful in prioritizing individuals. This study evaluated the suitability of a radiation portal monitor for such screening. A model of the portal monitor was created for use with models of six anthropomorphic phantoms in Monte Carlo N-Particle Transport Code Version 5 (MCNP) X-5 Monte Carlo Team (MCNP A General Monte Carlo N-Particle Transport Code Version 5. LA-CP-03-0245. Vol. 2. Los Alamos National Laboratory, 2004.). The count rates of the portal monitor were simulated for inhalation and ingestion of likely radionuclides from an RDD for each of the phantoms. The time-dependant organ concentrations of the radionuclides were determined using Dose and Risk Calculation Software Eckerman, Leggett, Cristy, Nelson, Ryman, Sjoreen and Ward (Dose and Risk Calculation Software Ver. 8.4. ORNL/TM-2001/190. Oak Ridge National Laboratory, 2006.). Portal monitor count rates corresponding to a committed effective dose E(50) of 10 mSv are reported.

Additional details

Publishing Information

Journal Title
Radiation Protection Dosimetry
Journal Issue
Issue 2012
Journal Page Range
p. 1
ISSN
0144-8420
CODEN
RPDODE

Optional Information

Contract/Grant/Project number
AC05-00OR22725
Funding organization
US Department of Energy (United States)