Relation between organ and whole body doses and local doses measured by ESR for standard and realistic neutron and photon external overexposures.
In the case of a radiological accident due to external exposure, the assessment of the organs and whole body dose received by the victim is fundamental information for therapeutic strategy. Two complementary dosimetric techniques based on physical means are used in routine practice in the laboratory: Monte Carlo (MC) calculations and ESR spectroscopy performed on materials removed from the victim. The aim of the present study is to provide data relevant for a quick assessment of the dose distribution in case of accidental overexposure using dose ESR measurements performed on one or several points of the body. The chosen configurations were, on the one hand, standard homogeneous exposures (ICPR 74) and, on the other hand, exposures typical of accidental situations (source at 1m, in a pocket, in a hand and contaminated floor). The study was performed for monoenergetic photons and neutrons, and several sources (60Co, 137Cs, 192Ir, 252Cf and AmBe).
Hervé
M L
ML
Institute for Radiological Protection and Nuclear Safety, BP 17 F-92262 Fontenay aux Roses Cedex, France.
Clairand
I
I
Trompier
F
F
Tikunov
D
D
Bottollier-Depois
J F
JF
D003198:Computer Simulation; D004578:Electron Spin Resonance Spectroscopy / Q000379:methods*; D004781:Environmental Exposure / Q000032:analysis*; D004867:Equipment Design; D019544:Equipment Failure Analysis; D006801:Humans; D038622:Internationality; D008954:Models, Biological; D009502:Neutrons; D009928:Organ Specificity; D017785:Photons; D011829:Radiation Dosage; D011834:Radiation Monitoring / Q000379:methods*; D011835:Radiation Protection / Q000379:methods*; D015203:Reproducibility of Results; D012680:Sensitivity and Specificity; D014915:Whole-Body Counting / Q000379:methods*