Preparation and properties of thermoluminescent materials

Azorı́n, J.; Furetta, C.; Scacco, A.

doi:10.1002/pssa.2211380102

Cited by 107 publications

(56 citation statements)

References 74 publications

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“…Materials studied were LiF:Mg, Cu,P; BaSO4:Dy; BaSO4:Eu which were prepared in our laboratory [3] and that commercially available ~-A1203 :C.…”

Section: Methodsmentioning

confidence: 99%

Thermoluminescence and optical properties of some dosimetric materials

Azorı́n

1997

Journal of Thermal Analysis

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Thermoluminescence and optical properties ofLiF:Mg,Cu,P; BaSO4:Dy; BaSO4; Eu and ~-A1203:C were investigated as a part of a broader research project on TL mechanisms in various materials. The effects of ionizing radiation on these phosphors are determined in this work by means ofthermoluminescence and optical absorption experiments with the aim of identifying new defects formed in these systems and of testing dosimetric characteristics.

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“…Materials studied were LiF:Mg, Cu,P; BaSO4:Dy; BaSO4:Eu which were prepared in our laboratory [3] and that commercially available ~-A1203 :C.…”

Section: Methodsmentioning

confidence: 99%

Thermoluminescence and optical properties of some dosimetric materials

Azorı́n

1997

Journal of Thermal Analysis

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“…Sedangkan Hp(7) yakni kedalaman 0.07mm yang menunjukan besar dosis ekivalen pada kulit. Dosimeter personal yang sering digunakan di Indonesia yaitu Termoluminesensi Dosimeter (TLD) karena relatif murah, kuat, kecil, dan dapat digunakan kembali setelah pembacaan TLD [2][3][4]. TLD secara konvensional digunakan untuk verifikasi dan mengukur radiasi [5][6][7].…”

Section: Pendahuluanunclassified

Simulation of TLD-700 (Lif; Mg, Ti) for Determination of Hp Equivalent Dose (10) on Radiation Workers (Gamma) with MCNPX Approach

Pradipta

Rianto²,

Bunawas

2017

Nat-B

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ABSTRAKPekerja radiasi wajib melakukan pemantauan dosis radiasi untuk mengurangi dampak radiasi pengion pada tubuh. Pemerintah melalui BAPETEN menetapkan dosis ekivalen maksimum untuk pekerja sebesar 20 mSv/tahun. Salah satu alat pantau personal yang banyak dipakai adalah TLD-700 (khususnya untuk radiasi gamma). Dosis ekivalen pada tubuh pekerja radiasi untuk kedalaman 10 mm (Hp(10)) dapat diperkirakan melalui pendekatan simulasi MCNPX. Untuk melakukan simulasi dibutuhkan input model geometri yang disesuaikan dengan geometri pada eksperimen. Hasil simulasi pada posisi sumber tegak lurus diperoleh laju dosis 8,565mSv/jam, yang menunjukan perbedaan sebesar 1,5% terhadap hasil eksperimen, sehingga dosis Hp (10) ABSTRACTRadiation workers are compulsory to monitoring radiation dose for reduce the effects of ionizing radiation on the body. Government through similar BAPETEN maximum dose for radiation workers is 20 mSv/year. One of the personal monitoring tool that is widely used is the TLD-700 (specially for gamma radiation). The equivalent dose to the worker's body to a depth of 10mm (Hp(10)) able to be predicted from a simulation approach MCNPX. To simulation needed input model of geometry which adapted to the geometry experiments. The simulation results at the source position vertical to the dose rate is obtained 8,565mSv/h, which shows a difference of 1.5% on the results of the experiment, so the Hp(10) dose can be determined. This experiment able to simulated for contamination source 137 Cs on the floor position unable to be done experimentely contamination source. Estimation through simulation, the dose rate on the floor at 14.920 mSv/h. The results showed the difference of dose rate through dose rate 75% vertical source larger than the vertical direction. According to the result need to be calibration TLD-700 for the source position from the bottom. Because the greater the dose rate (from below), the greater the Hp(10) dose is received. With the result clear that considerable potential MCNPX used to estimate personal Hp(10) dose for radiation workers, specially in relation to the case of a radiation accident.

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“…From this figure it follows that dosimeters based on this material should not be subject to temperatures above 80 o C, otherwise fading starts to occur. In addition to a simple glow curve, a linear dose response, high luminescence efficiency, low photon energy dependence and long term stability are also desirable for the application of thermoluminescent materials in radiation dosimetry (Azorin et al, 1993). Fig.…”

Section: Thermoluminescent Materialsmentioning

confidence: 99%

“…The thermoluminescence peak is located from 180 ºC to 260 ºC, offering an easy readout process. With an effective atomic number (Z eff ) close to that of soft biological tissue, LiF-based dosimeters are the most widely used thermoluminescence phosphors in personal radiation monitoring due to its very low photon energy dependence (Azorin et al, 1993). However, the glow curves of LiF-based dosimeters consist of at least seven peaks (Satinger et al, 1999).…”

Section: Thermoluminescent Materialsmentioning

confidence: 99%

“…Nakajima et al (Nakajima et al, 1978) first introduced the LiF:Mg, Cu, P (TLD-100H) which shows a 15 times greater sensitivity than that of the LiF:Mg, Cu (TLD-100). Furthermore, to improve the sensitivity of the dosimeters to thermal neutrons, 6 Li and 7 Li isotope based LiF dosimeters were designed to measure thermal neutrons in a mixed radiation field (Azorin et al, 1993). One of the better performers is CaSO 4 :Dy which is approximately 10 times more sensitive than LiF:Mg,Ti (TLD-100).…”

Section: Thermoluminescent Materialsmentioning

confidence: 99%

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