• 한국재료학회:학술대회논문집
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• 한국재료학회 1998년도 IUMRS-ICEM ABSTRACT BOOK
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• pp.119.2-119
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• 1998

• 대한치과의사협회지
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• 제50권7호
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• pp.420-430
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• 2012

Purpose: The purpose of this study was to measure the absorbed dose and to calculate the effective dose for full-mouth periapical radiography using the portable dental x-ray machine and panoramic radiography Material and Method: Thermoluminescent chips were placed at 25sites throughout the layers of the head and neck of a tissue-equivalent human skull phantom. The man phantom was exposed with the portable dental x-ray machine and panoramic unit. During full-mouth periapical radiography the exposure setting was 60 kVp, 2 mA and 0.15 ~ 0.25 seconds, while during panoramic radiography the selected exposure setting was 72 kVp, 8 mA and 18 seconds. Absorbed dose measurements were obtained and equivalent doses to individual organs were summed using ICRP 103 to calculate of effective dose. Result: In the full-mouth periapical radiography, the highest absorbed dose was recorded at the mandible body follow with submandibular glands and cheek. Using panoramic unit, the highest absorbed dose was parotid glands and the following was back of neck and submandibular glands. The effective dose in full-mouth periapical radiography using portable dental x-ray machine was 46 ${\mu}Sv$. In panoramic radiography, the effective dose was 38 ${\mu}pSv$. Conclusion: It was recommended to panoramic radiography for general check in the head and neck area because that the effect dose in the panoramic radiography was lower than the dose in the full-mouth periapical radiography using portable dental x-ray machine.

• 한국의학물리학회지:의학물리
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• 제2권1호
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• pp.17-28
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• 1991

방사선 피폭량을 정확히 측정하는 방법의 하나로 열형광선량계의 각 소자별 보정인자를 구하여 사용하는 방법이 있다. 열형광선량계를 기준 선량계, 제어선량계 및 현장 선량계의 3그룹으로 분류하여, 기준 선량계는 제어 및 현장 선량계의 소자보정인자 산출시에만 사용하며, 소자보정인자 산출을 위해 일부분씩 사용할 때를 제외하고는 안전한 장소에 보관한다. 소자보정인자는 기준 선량계의 반응도 평균치에 대한 각 소자의 반응도 비로서 정의된다. 선량계는 판독 횟수가 증가하거나 손상으로 인해 반응도가 감소하기 때문에 최초 구입할 때 또는 사용중에 소자보정 인자를 주기적으로 재산출하여야 한다. 이 소자보정방법은 새로운 선량계의 판독 오차를 줄이고 사용중인 선량계의 신뢰도를 향상시킬 수 있는 우수한 방법이다. 본 논문에서는 소자보정인자를 산출하기 위한 10가지 단계별 방법을 자세히 소개하였다.

• 한국방사선학회논문지
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• 제7권6호
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• pp.415-418
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• 2013

방사선을 조사한 시료를 가열하면 시료로부터 흡수된 에너지의 일부가 더 긴 파장의 빛으로 방출되는 것을 이용한 것이 열형광선량계이다. 본 연구의 목적은 피폭선량계로 널리 이용되는 8개의 TLD-100에 동일한 조건에서 열처리와 방사선을 조사하여 자기장을 노출하지 않은 4개와 자기장에 노출시킨 4개를 글로우 곡선을 분석 하였다. 실험 결과 방사선 조사로 포획된 전자가 자기장 노출에 의해 낮은 트랩의 전자들 중 일부는 가전자대의 정공과 결합하여 48%의 피크 면적이 감소하였다. 낮은 트랩의 면적 감소로 인하여 자기장에 노출된 TLD-100은 낮은 선량을 나타내었다. 또한 낮은 트랩의 활성화 에너지는 1.6 eV와 1.5 eV로 나타났다.

• Imaging Science in Dentistry
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• 제37권3호
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• pp.149-156
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• 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
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• 제42권2호
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• pp.65-70
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• 2012

Purpose : The aim of this study was to compare the effective dose for imaging of mandible between multi-detector computed tomography (MDCT) and cone-beam computed tomography (CBCT). An MDCT with low dose technique was also compared with them. Materials and Methods : Thermoluminescent dosimeter (TLD) chips were placed at 25 organ sites of an anthropomorphic phantom. The mandible of the phantom was exposed using 2 different types of MDCT units (Somatom Sensation 10 for standard-dose MDCT, Somatom Emotion 6 for low-dose MDCT) and 3 different CBCT units (AZ3000CT, Implagraphy, and Kavo 3D eXaM). The radiation absorbed dose was measured and the effective dose was calculated according to the ICRP 2007 report. Results : The effective dose was the highest for Somatom Sensation 10 (425.84 ${\mu}Sv$), followed by AZ3000CT (332.4 ${\mu}Sv$), Somatom Emotion 6 (199.38 ${\mu}Sv$), and 3D eXaM (111.6 ${\mu}Sv$); it was the lowest for Implagraphy (83.09 ${\mu}Sv$). The CBCT showed significant variation in dose level with different device. Conclusion : The effective doses of MDCTs were not significantly different from those of CBCTs for imaging of mandible. The effective dose of MDCT could be markedly decreased by using the low-dose technique.

• Journal of Radiation Protection and Research
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• 제30권4호
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• pp.231-236
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• 2005

열형광선량계의 TL 소자는 동일한 제조공정에 의해 생산되지만 소자의 반응도가 선량계 별로 편차가 있고, 반복사용 또는 외부로부터의 물리적 자극에 의해 반응도가 조금씩 감소한다. 이러한 반응도 감소를 기준선량제의 평균반응값에 맞추어지도록 보정해 주는 인자가 소자보정이자(ECF)이다. 열형광선량계(TLD)의 ECF 측정절차에 대해 자세히 기술하였으며 319개의 기준선량계, 교정용선량계, 현장선량제의 ECF를 3회 측정하여 평균값을 구하였다. 또한 3회 측정에 대한 %CV를 구하여 ECF 측정값을 검증하였다. 선량계 종류별 용도별로 ECF값의 부포를 구했으며, %CV값의 분포도 나타내었다. 현장선량계는 지난 3년동안 6회정도 사용되었는데 ECF값의 변화가 거의 없었고, 보다 빈번하게 사용된 교정용선량계의 ECF값은 평균 4.7% 증가하였다.

• 센서학회지
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• 제7권4호
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• pp.234-242
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• 1998

Czochralski 방법을 사용하여 격자결함이 적은 CsI 단결정 섬광체를 육성하기 위한 최적육성조건을 구하기 위하여 광투과율의 변화와 열형광특성을 이용하였다. 결정화과정을 반복할수록 불필요한 불순물 분포와 열형광강도 및 glow 피이크의 수가 감소하였다. 결정성장방향은 (110)이었고, 육성한 CsI의 결정구조는 체심입방체이었다. 그리고 격자상수는 $4.568{\AA}$ 임을 확인할 수 있었다. CsI:3rd의 활성화 에너지(trap깊이)는 약 0.45 eV 이었고, 주파수인자는 $5.18{\times}10^5\;sec^{-1}$이었다.

• Journal of Radiation Protection and Research
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• 제44권2호
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• pp.79-88
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• 2019

Background: The main goal of experiments is to compare various operational and technical characteristics of D-Shuttle semiconductor personal dosimeters of the Japanese company "Chiyoda Technol Corporation" and Harshaw thermoluminescent dosimeters (TLD) manufactured by "Thermo Fisher Scientific" and DTL-02 of the Russian Research and Production Enterprise (RPE) "Doza" by their occupational and calibration exposure at various dose equivalents from 0.5 to 20 mSv of gamma-radiation. Materials and Methods: Besides dosimeters DTL-02, D-Shuttle and Harshaw TLD, there were also used: (1) the primary reference radionuclide source Hopewell Designs IAEA: G10-1-12 with $^{137}Cs$ isotope (an error is not more than 6% and activity is 20 Ci), and (2) the verification device UPGD-2M of RPE "Doza" and installed in the National Center for Expertise and Certification of the Republic of Kazakhstan (Kapchagai, the National Center for Expertise and Certification). Results and Discussion: The main results of researches are the following: (1) TLDs for Harshaw 6600 and DVG-02TM have an approximately equal measurement accuracy of the individual dose equivalents in the range from 0.5 to 20 mSv of gamma-radiation. (2) Advantages of dosimeters for Harshaw 6600 are due to the high measurement productivity and opportunity to indicate the dose on the skin $H_p$(0.07). Advantages of DVG-02TM consist of operation simplicity and lower cost than of Harshaw 6600. (3) D-Shuttles are convenient for use in the current and the operational monitoring of ionizing radiation. Measurement accuracy and 10% linearity of measurements are ensured when D-Shuttle is irradiated with dose equivalents below 1 mSv at the equivalent dose rate not higher than $3mSv{\cdot}hr^{-1}$. This allows using D-Shuttle at a routine technological activity. Conclusion: The obtained results of experiments demonstrate advantages and disadvantages of D-Shuttle semiconductor dosimeters in comparison with two TLD systems of DVG-02TM and Harshaw 6600.

• 방사성폐기물학회지
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• 제21권3호
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• pp.371-381
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• 2023

Evaluating the effectiveness of the radiation protection measures deployed at the Centralized Radioactive Waste Management Facility in Ghana is pivotal to guaranteeing the safety of personnel, public and the environment, thus the need for this study. Radiagem^TM 2000 was used in measuring the dose rate of the facility whilst the personal radiation exposure of the personnel from 2011 to 2022 was measured from the thermoluminescent dosimeter badges using Harshaw 6600 Plus Automated TLD Reader. The decay store containing scrap metals from dismantled disused sealed radioactive sources (DSRS), and low-level wastes measured the highest dose rate of 1.06 ± 0.92 µSv·h^-1. The range of the mean annual average personnel dose equivalent is 0.41-2.07 mSv. The annual effective doses are below the ICRP limit of 20 mSv. From the multivariate principal component analysis biplot, all the personal dose equivalent formed a cluster, and the cluster is mostly influenced by the radiological data from the outer wall surface of the facility where no DSRS are stored. The personal dose equivalents are not primarily due to the radiation exposures of staff during operations with DSRS at the facility but can be attributed to environmental radiation, thus the current radiation protection measures at the Facility can be deemed as effective.