Polycarbonate-based benzo-δ-sultam films for high-dose dosimetry in radiation processing
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Shazad Feizi
und
Mehdi Ghandi
Abstract
In this work characteristics of the polycarbonate films with 20 μm in thickness containing different weight percentage of Benzo-δ-sultam were studied for use as a high dose dosimetry system in radiation processing facilities. The sensitivity of the dosimeters and the linearity of dose-response curves were investigated under 60Co γ-rays in a dose range of 0–100 kGy, and obtained results were compared with the commercial CTA and FWT film dosimeters. The results show that the absorbance at 348 nm depends linearly on the dose in the investigated dose range. The effects of pre-irradiation (shelf-life) and post-irradiation storage in dark and in indirect sunlight are also discussed. The results show that the dosimeters characteristics are stable within 1% at 25 ℃, 3 months after the irradiation.
©2014 Walter de Gruyter Berlin/Boston
Artikel in diesem Heft
- Frontmatter
- Measurement of cross section of the 98Mo(n, γ)99Mo reaction using monochromatic thermal neutrons
- A new 2-oxy-N,N-dioctylacetamide grafted resin for the separation of trivalent actinides from nitric acid medium
- Mixer-settler runs for the evaluation of tri-iso-amyl phosphate (TiAP) as an alternate extractant to tri-n-butyl phosphate (TBP) for reprocessing applications
- Comparative study on the production of 68Ga from proton induced reactions on different targets: Evaluation of experimental data and model calculations
- Development of a production scale purification of Ge-68 from irradiated gallium metal
- New neutral and lipophilic technetium complexes based on a cytectrene moiety: synthesis, characterization and biological evaluation
- Degradation of morphine and codeine by gamma radiation in methanol solution
- Polycarbonate-based benzo-δ-sultam films for high-dose dosimetry in radiation processing
- Modeling of physico–chemical characteristics of concrete for filling trenches in radioactive waste management
Artikel in diesem Heft
- Frontmatter
- Measurement of cross section of the 98Mo(n, γ)99Mo reaction using monochromatic thermal neutrons
- A new 2-oxy-N,N-dioctylacetamide grafted resin for the separation of trivalent actinides from nitric acid medium
- Mixer-settler runs for the evaluation of tri-iso-amyl phosphate (TiAP) as an alternate extractant to tri-n-butyl phosphate (TBP) for reprocessing applications
- Comparative study on the production of 68Ga from proton induced reactions on different targets: Evaluation of experimental data and model calculations
- Development of a production scale purification of Ge-68 from irradiated gallium metal
- New neutral and lipophilic technetium complexes based on a cytectrene moiety: synthesis, characterization and biological evaluation
- Degradation of morphine and codeine by gamma radiation in methanol solution
- Polycarbonate-based benzo-δ-sultam films for high-dose dosimetry in radiation processing
- Modeling of physico–chemical characteristics of concrete for filling trenches in radioactive waste management
