Retrospective Dosimetry and Dose Reconstruction of Ionizing Radiation

Author(s):  
V.V. Chumak
2013 ◽  
Vol 89 (9) ◽  
pp. 741-749 ◽  
Author(s):  
Charles Kirkby ◽  
Esmaeel Ghasroddashti ◽  
Anna Kovalchuk ◽  
Bryan Kolb ◽  
Olga Kovalchuk

2020 ◽  
Vol 12 (552) ◽  
pp. eaaw5831
Author(s):  
Marshleen Yadav ◽  
Sagar Bhayana ◽  
Joseph Liu ◽  
Lanchun Lu ◽  
Jason Huang ◽  
...  

Nuclear radiation and radioactive fallouts resulting from a nuclear weapon detonation or reactor accidents could result in injuries affecting multiple sensitive organs, defined as acute radiation syndrome (ARS). Rapid and early estimation of injuries to sensitive organs using markers of radiation response is critical for identifying individuals who could potentially exhibit ARS; however, there are currently no biodosimetry assays approved for human use. We developed a sensitive microRNA (miRNA)–based blood test for radiation dose reconstruction with ±0.5 Gy resolution at critical dose range. Radiation dose–dependent changes in miR-150-5p in blood were internally normalized by a miRNA, miR-23a-3p, that was nonresponsive to radiation. miR-23a-3p was not highly expressed in blood cells but was abundant in circulation and was released primarily from the lung. Our assay showed the capability for dose estimation within hours to 1 week after exposure using a drop of blood from mice. We tested this biodosimetry assay for estimation of absorbed ionizing radiation dose in mice of varying ages and after exposure to both improvised nuclear device (IND)–spectrum neutrons and gamma rays. Leukemia specimens from patients exposed to fractionated radiation showed depletion of miR-150-5p in blood. We bridged the exposure of these patients to fractionated radiation by comparing responses after fractionated versus single acute exposure in mice. Although validation in nonhuman primates is needed, this proof-of-concept study suggests the potential utility of this assay in radiation disaster management and clinical applications.


Author(s):  
Marjori L. Camparoto ◽  
Adriana T. Ramalho ◽  
Adayapalam T. Natarajan ◽  
Maria P. Curado ◽  
Elza T. Sakamoto-Hojo

2019 ◽  
Vol 22 ◽  
pp. 113
Author(s):  
K. Stamoulis ◽  
K. G. Ioannides ◽  
H. Bakola ◽  
C. A. Papachristodoulou ◽  
L. M. Tsodoulos

Following a large-scale nuclear event, a quantitative estimate of the radiation dose to the general population necessitates the availability of adequate procedures for the assessment of doses. The main objectives of dose reconstruction, namely retrospective dosimetry can be synoptically stated as in the following: a) To guide the provision of proper protection for the population that had been exposed to radiation, b) To provide assuring information to the worrying public and c) To provide input data for epidemiological studies. Amongst the methods used for dose estimation are the Thermoluminescence (TL) and the Optically Stimulated Luminescence (OSL). Methods based on TL and OSL have the advantage that they allow the measurement of the integrated absorbed dose. When the irradiation comes from external sources, materials found within the perimeter of the accident area such as bricks, tiles and pottery and certain household chemicals, can be used. The absorbed dose may be evaluated many years after the accident.


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