Passive solid state dosimeters, such as thermoluminescence dosimeters,
provide integrated measurement of the total dose and are widely used in
environmental monitoring programs. The objective of this paper
is to provide a comprehensive review on the use of thermoluminescent dosimetry methods for monitoring radiation dose in the environment. The
article presents the part of the research results of the project PREPAREDNESS (EMPIR 2016 call for Metrology for Environment joint research project)
with a particular objective to harmonize procedures used by
dosimetry services, relevant authorities and Institutes across the Europe. To
achieve this, different monitoring routines that are based on passive environ
mental dosimetry methods are investigated. Differences in performing
specific steps such as preheating, reading, annealing, minimizing fading, and others, are analyzed. The investigation was performed by
means of qualitative literature review that showed the lack of information about specific steps. The conclusion of this work is that
thermoluminescent dosimetry measurement system has to be type-tested
even though the testing procedure is complicated. In addition to this,
control dosimeters should be introduced, International Organization
for Standardization protocols should be followed during calibration, and
finally, parameters influencing the measurement uncertainty have to be
identified and well understood in order to pro duce ac cu rate dose measurement results.
The objective of this work is to assess patient organ doses, effective doses and entrance surface doses in conventional diagnostic radiology procedures for standard adult patient. The survey consists of measurements of doses delivered to 239 patients in nine types of X-ray examinations. Three types of data were collected: X-ray machine data, patient data, and output measurements. Entrance surface dose was assessed based on the survey data and subsequently, using conversion coefficients, the organ doses and effective doses were calculated. Values of the entrance surface dose and the effective dose were estimated to be 0.4 to 5.8 mGy and 0.03 to 3.00 mSv for different examinations. Derived doses were compared with recommended general diagnostic reference levels. The impact of examination parameters on dose values was discussed. Except for posterior-anterior chest examination, all estimated doses are lower than stated reference levels. Survey data are aimed at helping development of national quality control and radiation protection programmed for medical exposures
tri cal En gi neer ing, Uni ver sity of Bel grade, Bel grade, Ser bia 2 Vin~a In sti tute of Nu clear Sci ences, Uni ver sity of Bel grade, Bel grade, Ser bia 3 In sti tute of Gen eral and Phys i cal Chem is try, Uni ver sity of Bel grade, Bel grade, Ser bia Sci en tific pa per
and Ra di a tion Hy giene, Fac ulty of Vet er i nary Med i cine, Uni ver sity of Bel grade, Bel grade, Ser bia 2 Ra di a tion Pro tec tion De part ment, Vin~a In sti tute of Nu clear Sci ences, Uni ver sity of Bel grade, Bel grade, Ser bia 3 De part ment of Phys i ol ogy, In sti tute for Bi o log i cal Re search "Siniša Stankovi}", Uni ver sity of Bel grade, Bel grade, Ser bia Sci en tific pa per
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