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VISUALISATION AND QUANTIFICATION OF LUNG CONTENT OF RADIONUCLIDES ASSOCIATED WITH NUCLEAR AND RADIOLOGICAL EMERGENCIES.

Hansson, Mats LU and Rääf, Christopher LU (2011) In Radiation Protection Dosimetry 145. p.341-350
Abstract
In a situation when radionuclides accidentally or deliberately are dispersed in the environment, there is a need for rapid investigation of the internal contamination in exposed individuals. In this work, the possibilities of visualising and quantifying uptakes of different radionuclides in the lung region of an adult individual using gamma camera systems have been examined, mainly on a two-headed stationary clinical gamma camera. An anthropomorphic phantom was used to mimic acute lung uptakes in three different body sizes. The gamma camera was calibrated with the lung inserts filled with a homogeneous solution of (99)Tc(m), (46)Sc and (32)P, or with point sources of (241)Am, (57)Co, (85)Sr, (137)Cs and (90)Sr/(90)Y. It was found that for... (More)
In a situation when radionuclides accidentally or deliberately are dispersed in the environment, there is a need for rapid investigation of the internal contamination in exposed individuals. In this work, the possibilities of visualising and quantifying uptakes of different radionuclides in the lung region of an adult individual using gamma camera systems have been examined, mainly on a two-headed stationary clinical gamma camera. An anthropomorphic phantom was used to mimic acute lung uptakes in three different body sizes. The gamma camera was calibrated with the lung inserts filled with a homogeneous solution of (99)Tc(m), (46)Sc and (32)P, or with point sources of (241)Am, (57)Co, (85)Sr, (137)Cs and (90)Sr/(90)Y. It was found that for the stationary gamma camera the minimum detectable activity in the lungs using a 5-min acquisition time ranged from 0.53 kBq for (46)Sc to 50 kBq for (32)P. Furthermore, the point sources of (137)Cs, (60)Co and (90)Sr/(90)Y (0.16, 0.80 and 2.2 MBq, respectively) located in the lung insert of the phantom, could be clearly visualised, exhibiting distinct intensity maxima. It is thus concluded that gamma camera systems can be useful for rapid assessment of acute intakes of radionuclides associated with emergency preparedness, both in terms of localisation and quantification. (Less)
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author
organization
publishing date
type
Contribution to journal
publication status
published
subject
in
Radiation Protection Dosimetry
volume
145
pages
341 - 350
publisher
Nuclear Technology Publishing
external identifiers
  • wos:000291065800002
  • pmid:21196466
  • scopus:79957794868
ISSN
1742-3406
DOI
10.1093/rpd/ncq438
language
English
LU publication?
yes
id
553c5d74-4ef6-4520-a24d-21e1af467d3d (old id 1777918)
alternative location
http://www.ncbi.nlm.nih.gov/pubmed/21196466?dopt=Abstract
date added to LUP
2011-02-01 10:11:04
date last changed
2017-01-01 07:50:42
@article{553c5d74-4ef6-4520-a24d-21e1af467d3d,
  abstract     = {In a situation when radionuclides accidentally or deliberately are dispersed in the environment, there is a need for rapid investigation of the internal contamination in exposed individuals. In this work, the possibilities of visualising and quantifying uptakes of different radionuclides in the lung region of an adult individual using gamma camera systems have been examined, mainly on a two-headed stationary clinical gamma camera. An anthropomorphic phantom was used to mimic acute lung uptakes in three different body sizes. The gamma camera was calibrated with the lung inserts filled with a homogeneous solution of (99)Tc(m), (46)Sc and (32)P, or with point sources of (241)Am, (57)Co, (85)Sr, (137)Cs and (90)Sr/(90)Y. It was found that for the stationary gamma camera the minimum detectable activity in the lungs using a 5-min acquisition time ranged from 0.53 kBq for (46)Sc to 50 kBq for (32)P. Furthermore, the point sources of (137)Cs, (60)Co and (90)Sr/(90)Y (0.16, 0.80 and 2.2 MBq, respectively) located in the lung insert of the phantom, could be clearly visualised, exhibiting distinct intensity maxima. It is thus concluded that gamma camera systems can be useful for rapid assessment of acute intakes of radionuclides associated with emergency preparedness, both in terms of localisation and quantification.},
  author       = {Hansson, Mats and Rääf, Christopher},
  issn         = {1742-3406},
  language     = {eng},
  pages        = {341--350},
  publisher    = {Nuclear Technology Publishing},
  series       = {Radiation Protection Dosimetry},
  title        = {VISUALISATION AND QUANTIFICATION OF LUNG CONTENT OF RADIONUCLIDES ASSOCIATED WITH NUCLEAR AND RADIOLOGICAL EMERGENCIES.},
  url          = {http://dx.doi.org/10.1093/rpd/ncq438},
  volume       = {145},
  year         = {2011},
}