Study of the use of polycarbonate for determining high doses of ionizing radiation
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F24%3AN0000196" target="_blank" >RIV/26722445:_____/24:N0000196 - isvavai.cz</a>
Result on the web
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DOI - Digital Object Identifier
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Alternative languages
Result language
angličtina
Original language name
Study of the use of polycarbonate for determining high doses of ionizing radiation
Original language description
Dosimetry of high doses of ionizing radiation is widely used not only in the field of basic and applied research, but also in a wide variety of industries. Examples of high-dose irradiation include food sterilization and shelf-life extension, single-use tools and materials, waste, antiquities attacked by wood decay organisms, biological and genetic research, inhibition of seed germination, retardation of fruit ripening. Furthermore, testing the radiation resistance of materials, defectoscopy, geological survey (coring), industrial irradiation of materials (e.g. cross-linking and grafting of polymers under the action of ionizing radiation), and last but not least, of course, nuclear energy, etc. In this work, the dosimetric properties of polycarbonate are studied and compared with a standardized and certified method using alanine dosimeters. Highly active 60Co is used as a gamma radiation source, neutron dosimetry was studied at the LVR-15 research nuclear reactor. The work is focused on researching the possibilities of using polycarbonate as a reusable integrating dosimeter operating on the basis of the radiochromic (coloring) phenomenon. The detection interval of the method for gamma radiation lies in the range of 1 - 200 kGy with an accuracy of 3%. In principle, it is possible to determine doses from 0.1 kGy to 300 kGy, where, however, it is necessary to take into account uncertainties in the order of several tens of percent. For dosimetry of high doses of neutron and gamma radiation, the change in optical density is an easily and cheaply measurable parameter, even in the field, using a hand-held portable densitometer. In this area, the use of solid-state organic radiochromic dosimeters is therefore much simpler than the use of alanine or gel dosimeters, which require very time- and financially demanding laboratory methods (electron paramagnetic resonance or nuclear magnetic resonance) for their evaluation. The goal of the work is to replace the above-mentioned expensive evaluation methods, roughly two orders of magnitude cheaper, with optical densitometry, which will provide the necessary results in tens of seconds, either through a desktop scanner or even a portable hand-held densitometer. The work also examines the time course of spontaneous regeneration of irradiated samples (fading) due to the possibility of reading the dose after a longer period (days to weeks) after irradiation. Furthermore, the possibility of artificially accelerating the regeneration of irradiated dosimeters (annealing) due to their repeatable usability (similar to, for example, TLD or OSL), which would make the method even cheaper.
Czech name
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Czech description
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Classification
Type
O - Miscellaneous
CEP classification
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OECD FORD branch
20501 - Materials engineering
Result continuities
Project
<a href="/en/project/LM2023041" target="_blank" >LM2023041: Czech International Centre of Research Reactors</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2024
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů