GUIDANCE ON THE USE OF HANDHELD SURVEY METERS FOR RADIOLOGICAL TRIAGE: TIME-DEPENDENT DETECTOR COUNT RATES CORRESPONDING TO 50, 250, AND 500 mSV EFFECTIVE DOSE FOR ADULT MALES AND ADULT FEMALES

被引:11
作者
Bolch, Wesley E. [1 ]
Hurtado, Jorge L. [2 ]
Lee, Choonsik [3 ]
Manger, Ryan [4 ]
Burgett, Eric [4 ]
Hertel, Nolan [4 ]
Dickerson, William [5 ]
机构
[1] Univ Florida, J Crayton Pruitt Family Dept Biomed Engn, Adv Lab Radiat Dosimetry Studies ALRADS, Gainesville, FL 32611 USA
[2] Univ Florida, Dept Nucl & Radiol Engn, Gainesville, FL 32611 USA
[3] NCI, Div Canc Epidemiol & Genet, Bethesda, MD 20852 USA
[4] Georgia Inst Technol, Dept Mech Engn, Atlanta, GA 30332 USA
[5] Armed Forces Radiobiol Res Inst, Bethesda, MD 20889 USA
来源
HEALTH PHYSICS | 2012年 / 102卷 / 03期
关键词
accident analysis; contamination; internal; dose assessment; emergency planning; PHANTOMS;
D O I
10.1097/HP.0b013e3182351660
中图分类号
X [环境科学、安全科学];
学科分类号
08 ; 0830 ;
摘要
In June 2006, the Radiation Studies Branch of the Centers for Disease Control and Prevention held a workshop to explore rapid methods of facilitating radiological triage of large numbers of potentially contaminated individuals following detonation of a radiological dispersal device. Two options were discussed. The first was the use of traditional gamma cameras in nuclear medicine departments operated as makeshift whole-body counters. Guidance on this approach is currently available from the CDC. This approach would be feasible if a manageable number of individuals were involved, transportation to the relevant hospitals was quickly provided, and the medical staff at each facility had been previously trained in this non-traditional use of their radiopharmaceutical imaging devices. If, however, substantially larger numbers of individuals (100's to 1,000's) needed radiological screening, other options must be given to first responders, first receivers, and health physicists providing medical management. In this study, the second option of the workshop was investigated-the use of commercially available portable survey meters (either NaI or GM based) for assessing potential ranges of effective dose (<50, 50-250, 250-500, and >500 mSv). Two hybrid computational phantoms were used to model an adult male and an adult female subject internally contaminated with Am-241, Cs-60, Cs-137, I-131, or Ir-192 following an acute inhalation or ingestion intake. As a function of time following the exposure, the net count rates corresponding to committed effective doses of 50, 250, and 500 mSv were estimated via Monte Carlo radiation transport simulation for each of four different detector types, positions, and screening distances. Measured net count rates can be compared to these values, and an assignment of one of four possible effective dose ranges could be made. The method implicitly assumes that all external contamination has been removed prior to screening and that the measurements be conducted in a low background, and possibly mobile, facility positioned at the triage location. Net count rate data are provided in both tabular and graphical format within a series of eight handbooks available at the CDC website (http://www.bt.cdc.gov/radiation/clinicians/evaluation). Health Phys. 102(3): 305-325; 2012
引用
收藏
页码:305 / 325
页数:21
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