• Nuclear Engineering and Technology
• /
• v.6 no.1
• /
• pp.3-8
• /
• 1974

The annealing of natural beryl powder used for the thermoluminescent dosimetry was investigated in order to eliminate effect of previous exposure. Through the glow curve analysis, the optimal annealing treatment was found to be one hour annealing at 145$0^{\circ}C$, but annealing for one hour at 55$0^{\circ}C$ was sufficient for reuse of natural beryl powder. There are two distinguished glow peaks at $65^{\circ}C$ and 20$0^{\circ}C$ of heating temperature during readout process. The $65^{\circ}C$ glow peak fades away rapidly, but the 20$0^{\circ}C$ glow peak remains very stable. It is, therefore, quite feasible to use the 20$0^{\circ}C$ glow peak for thermoluminescent dosimetry.

• Journal of Radiation Protection and Research
• /
• v.9 no.1
• /
• pp.3-10
• /
• 1984

The properties of $Al_2O_3$ thermoluminescent phosphor have been observed to apply for gamma dosimetry in vivo. Glow peaks at 380, 420, 490 kelvin temperature with emission in the blue region have been detected and calculated as 1.4 eV the activation energy by means of heat response rising time method. Sensitization and supralinearity in $Al_2O_3$ phosphor could be consistently explained by the deep trap model. Studies of the thermoluminescence growth rate with gamma ray exposure showed linearly to $10^4$ Roentgen and then supralinear rate detected 1.2 power of exposure dose sensitization of $Al_2O_3$ is described five times more than TLD-100 and the fading time is shorter and then tried to apply for gamma dosimetry in vivo.

• Nuclear Engineering and Technology
• /
• v.7 no.3
• /
• pp.191-198
• /
• 1975

A study was made on the neutron dosimetry in a mixed gamma-neutron field with LiF thermoluminescent dosimeter. In order to estimate the neutron dose in a mixed field, $^{6}$ LiF and $^{7}$ LiF dosimeters were used for fast and thermal neutron doses. The over-all conversion factors for the effects of dosimeter positions were derived for personnel monitoring and the glow curves of the LiF dosimeters for neutron and gamma-ray doses were also analyzed.

• Nuclear Engineering and Technology
• /
• v.2 no.4
• /
• pp.229-239
• /
• 1970

Various thermoluminescent properties of Korean natural quartz for possible use in ${\gamma}$-ray dosimetry has been studied. If the heating is exactly linear, ${\gamma}$-irradiated radiation sensitive (type 1) $\alpha$-quartz can yield a glow curve of single peak, hence glow peak height could be taken as a ${\gamma}$-dose for its dosimetry. Quartz crystal dosimeter exhibited the linearity of thermoluminescent intensity in the range from about 2$\times$10$^{3}$R to 2$\times$10$^{6}$ R, and also had an advantage of low fading because of the high peak temperature (300$\pm$4$0^{\circ}C$). The pulverized quartz sample having the grain size of 0.3<ø<0.9mm showed the linearity of T. L. intensity in the range from 50R to 2$\times$10$^3$R. Therapeutic application of the pulverized sample on the correct measurement of the absorbed dose in a body region of a cancer patient seems to be successful.

• Journal of radiological science and technology
• /
• v.14 no.1
• /
• pp.49-60
• /
• 1991

Thermoluminescent phosphors, which are now being used widely in radiation dosimetry, have an excellent sensitivity to ionizing radiation. In this study, thermoluminescent phosphors of $CaSO_4$ : Mn, $CaSO_4$ : Dy and $CaSO_4$ : Tm are prepared and their physical properties are investigated by measuring the trapping parameters and their luminescent spectra. By considering the sensitivity to X-ray and fading characteristics, $CaSO_4$ : Dy is most adequate to imaging plate. The imaging plate are prepared by coating the $CaSO_4$ : Dy powder on the Al substrate and its dose dependence is linear within the range of 40 mGy-20 Gy X-ray. The sensitivity of imaging plate depends linearly on the thickness of coated phosphor layer up to $35\;mg/cm^2$ and is independent on the grain size of the phosphor in the range of $70{\sim}250\;{\mu}m$. By photographing the imaging plate, X-ray images of the test object are obtained and better than those of X-ray films.

• Journal of Radiation Protection and Research
• /
• v.48 no.4
• /
• pp.197-203
• /
• 2023

Background: The thermoluminescent dosimeter (TLD) and Monte Carlo (MC) dosimetry are carried out to determine the occupational dose for personnel in the handling of ¹²⁵I seed sources. Materials and Methods: TLDs were placed in different layers of the Alderson-Rando phantom in the thyroid, lung and also eyes and skin surface. An ¹²⁵I seed source was prepared and its activity was measured using a dose calibrator and was placed at two distances of 20 and 50 cm from the Alderson-Rando phantom. In addition, the Monte Carlo N-Particle Extended (MCNPX 2.6.0) code and a computational phantom with a lattice-based geometry were used for organ dose calculations. Results and Discussion: The comparison of TLD and MC results in the thyroid and lung is consistent. Although the relative difference of MC dosimetry to TLD for the eyes was between 4% and 13% and for the skin between 19% and 23%, because of the existence of a higher uncertainty regarding TLD positioning in the eye and skin, these inaccuracies can also be acceptable. The isodose distribution was calculated in the cross-section of the head phantom when the ¹²⁵I seed was at two distances of 20 and 50 cm and it showed that the greatest dose reduction was observed for the eyes, skin, thyroid, and lungs, respectively. The results of MC dosimetry indicated that for near the head positions (distance of 20 cm) the absorbed dose rates for the eye lens, eye and skin were 78.1±2.3, 59.0±1.8, and 10.7±0.7 µGy/mCi/hr, respectively. Furthermore, we found that a 30 cm displacement for the ¹²⁵I seed reduced the eye and skin doses by at least 3- and 2-fold, respectively. Conclusion: Using a computational phantom to monitor the dose to the sensitive organs (eye and skin) for personnel involved in the handling of ¹²⁵I seed sources can be an accurate and inexpensive method.

• Proceedings of the KIEE Conference
• /
• 1996.11a
• /
• pp.468-470
• /
• 1996

The use of thermoluminescent dosimeters (TLDs) for beta dosimetry has been encumbered by the energy-dependent responses of TLDs to beta radiation. This energy-dependent response is due to the low penetrating ability of beta particles. Thus the determination of the beta dose imparted to an exposed TLD chip can be accurately determined only if the energy distribution of beta radiation is correctly accounted for. So precise beta dosimeter used TLD chips place under several aluminum filters of varying thicknesses and developed to correctly determine doses due to radiation fields where the beta energy distribution is unknown.

• Imaging Science in Dentistry
• /
• v.37 no.3
• /
• pp.149-156
• /
• 2007

Purpose: The purpose of this study was to measure the absorbed dose and to calculate the effective dose for periapical radiography done by portable intraoral x-ray machines. Materials and Methods: 14 full mouth, upper posterior and lower posterior periapical radiographs were taken by wall-type 1 and portable type 3 intraoral x-ray machines. Thermoluminescent dosemeters were placed at 23 sites at the layers of the tissue-equivalent ART woman phantom for dosimetry. Average tissue absorbed dose and radiation weighted dose were calculated for each major anatomical site. Effective dose was calculated using 2005 ICRP tissue weighted factors. Results: On 14 full mouth periapical radiographs, the effective dose for wall-type x-ray machine was 30 Sv; for portable x-ray machines were 30 Sv, 22 Sv, 36 Sv. On upper posterior radiograph, the effective dose for wall-type x-ray machine was 4 Sv; for portable x-ray machines doses were 4 Sv, 3 Sv, 5 Sv. On lower posterior radiograph, the effective dose for wall type x-ray machine was 5 Sv; for portable x-ray machines doses were 4 Sv, 4 Sv, 5 Sv. Conclusion: Effective doses for periapical radiographs performed by portable intraoral x-ray machines were similar to doses for periapical radiographs taken by wall type intraoral x-ray machines.

• Imaging Science in Dentistry
• /
• v.37 no.2
• /
• pp.93-102
• /
• 2007

Purpose: Cone beam computed tomography (CBCT) provides a lower dose and cost alternative to conventional CT, promising to revolutionize the practice of oral and maxillofacial radiology. The purpose of this study was to evaluate the absorbed and effective doses of Implagraphy and VCT (Vatech Co., Hwasung, Korea) and compare them with those of panoramic radiography. Materials and Methods: Thermoluminescent dosimeter (TLD) chips were placed at 27 sites throughout the layers of Female ART Head and Neck Phantom for dosimetry. Implagraphy, VCT units, and Planmeca Proline XC panoramic unit were used for radiation exposures. Radiation weighted doses and effective doses were measured and calculated using 1990 and 2005 ICRP tissue weighting factors. Results: Effective doses in Sv (ICRP 2005, ICRP 1990) were 90.19, 61.62 for Implagraphy at maxillay molar area, 123.20, 90.02 for Implagraphy at mandibular molar area, 183.55, 139.26 for VCT and 40.92, 27.16 for panoramic radiography. Conclusion: Effective doses for VCT and Implagraphy were only about 2.2 to 4.5 times greater than those for panoramic radiography. VCT and Implagraphy, CBCT machines recently developed in Korea, showed moderately low effective doses.

• Journal of Korean Academy of Oral and Maxillofacial Radiology
• /
• v.29 no.2
• /
• pp.411-416
• /
• 1999

Purpose : This study was done to evaluate the absorbed doses in organs of the head and neck for the conventional temporomandibular joint tomography. Materials and Methods : Dosimetry was performed with 32 LiF thermoluminescent dosimeters, which were placed in a tissue-equivalent phantom when the temporomandibular joint was examined by both lateral and frontal temporomandibular joint tomography. Results : For lateral tomography, parotid gland and preauricular area towards tube showed relatively high absorbed dose of 1056.9 μGy and 519.9 μGy respectively. For frontal tomography, the two largest absorbed doses were 259.2 μGy in orbit towards tube and 212.0 μGy in lens towards tube. Conclusion : Conventional temporomandibular joint tomography showed relatively low absorbed doses on critical organs. Thus, responsible use of it may not be limited.