Study of the response reduction of LiF:Mg, Ti dosimeter for high dose dosimetry
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F. Torkzadeh
Abstract
A single crystal and 5 polycrystalline samples of LiF:Mg, Ti and their pellets were prepared and investigated so as to apply thermoluminescence high gamma dose dosimetry. Three zones of single crystal with dopant concentrations of 200 ppm of Mg and 20 ppm of Ti were also used to prepare the single crystal samples. For polycrystalline samples, dopant concentrations of 0.062 mol% Mg and Ti concentrations in the range of 0.016 and 0.046 mol% were used. All the samples were exposed to gamma doses of 1 kGy to 700 kGy and their response changes were determined by a gamma dose test of about 60 mGy. According to the results obtained, the use of response reduction by curve-fitting up to about 300 kGy can be performed reliably for high dose gamma dosimetry.
Kurzfassung
Eine Einkristall-Probe und 5 Polykristall-Proben aus LiF:Mg, Ti wurden vorbereitet für den Einsatz in der Thermolumineszenz Hochdosis-Dosimetrie untersucht. Drei Zonen des Einkristalls mit Dotierungskonzentrationen 200 ppm Mg und 20 ppm Ti für die Herstellung der Einkristall-Proben wurden verwendet. Für die Herstellung der Polykristall-Proben wurden Dotierungskonzentationen von 0.06 mol% Mg- und Ti-Konzentrationen zwischen 0.016 und 0.046 mol% benutzt. Alle Proben wurden mit Gammadosen im Bereich von 1 kGy bis 700 kGy bestrahlt und ihre Empfindlichkeitsänderung durch eine Gammadosis- Bestrahlung von etwa 60 mGy bestimmt. Auf der Basis der erhaltenen Ergebnisse, kann die Empfindlichkeitsabnahme unter Verwendung einer Kurvenpassung bis ungefähr 300 kGy zuverlässig für den Einsatz in der Hochdosis-Dosimetrie verwendet werden.
References
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© 2017, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- SIMULATE-3 K coupled code applications
- Application of the new IAPWS Guideline on the fast and accurate calculation of steam and water properties with the Spline-Based Table Look-Up Method (SBTL) in RELAP-7
- Simulation of water hammer phenomena using the system code ATHLET
- New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses
- Sensitivity analysis for thermo-hydraulics model of a Westinghouse type PWR: verification of the simulation results
- Calculation of the fuel temperature coefficient of reactivity considering non-uniform radial temperature distribution in the fuel rod
- The effect of boron dilution transient on the VVER-1000 reactor core using MCNP and COBRA-EN codes
- Modelling of the spent fuel heat-up in the spent fuel pools using one-dimensional system codes and CFD codes
- Optimization and analysis of the effects of physical parameters in a TRIGA-ADSR
- A comparison study for mass attenuation coefficients of some amino acids using MCNP code
- Validation of radioactive isotope activity measurement in homogeneous waste drum using Monte Carlo codes
- Study of the response reduction of LiF:Mg, Ti dosimeter for high dose dosimetry
- Non-contact micro mass evaluation method using an X-ray microscope
