• Journal of Radiation Protection and Research
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• 제31권2호
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• pp.97-104
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• 2006

최근 방사선 치료 및 진단 분야에서 선량 측정을 위하여 다양하게 사용되고 있는 MOSFET 선량계는 검출부위가 실리콘으로 이루어져 있으며 다른 검출기들과 마찬가지로 어느 정도의 에너지 의존도와 방향 의존도를 보인다. 따라서 MOSFET 선량제가 공기 중이 아닌 모의피폭체 내에서 선량 측정에 사용될 경우 낮은 에너지를 갖는 산란 광자 등 이차 광자들로 인하여 선량을 실제보다. 높게 평가하게 된다. 본 연구에서는 MOSFET 선량계의 에너지 의존도와 방향 의존도로 인하여 발생하는 오차를 보정하기 위한 선량보정인자를 몬테카를로 전산모사 기법을 이용하여 계산하였다. 먼저 사용되는 인형 모의 피폭체의 체적소 모의피폭체(Voxel Phanom)를 CT 영상을 이용하여 제작하였으며 제작된 체적소 모의 피폭체를 몬테카를로 전산코드로 구현한 후, 모의피폭체 내 각 선량계 지점에서 입사하는 광자의 에너지 및 방향별 에너지 스펙트럼을 계산하였다. 각각의 선량계 지점에서 0.662 MeV와 1.25 MeV의 광자빔을 고려하였으며 또한 MOSFET 선량계의 방향은 실리콘 베이스 방향과 에폭시 방향을 고려하였다. 주어진 선량제 지점에서의 선량보정인자는 계산된 에너지 의존도들의 중간간을 이용하여 결정하였으며 이렇게 결정된 각 선량계 지점에서 선량보정인자는 0.89-0.97 범위의 값들을 나타내었다. 본 연구결과에 따르면 MOSFET 선량계를 이용하여 인형 모의피폭체 내에 선량을 측정할 때 에너지 의존도와 방향 의존도를 고려하지 않을 경우 측정 위치에 따라 $3{\sim}11%$ 정도의 측정오차가 발생할 수 있다. 그러므로 인형 모의피폭체 내의 선량을 정확하게 측정하기 위해서는 선량보정인자를 각 선량계에 필히 적용해주어야 한다.

• 센서학회지
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• 제20권2호
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• pp.96-101
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• 2011

In this study, we fabricated a fiber-optic phantom dosimeter by arraying square type of plastic optical fibers in a PMMA phantom for measuring relative depth doses of therapeutic photon beams. To minimize the cross-talk between fiber-optic dosimeters, we selected appropriate septum by measuring leaked scintillating lights according to the various kinds of septa. In addition, we measured percentage depth doses of 6, 15 MV photon beams using a fiber-optic phantom dosimeter.

• 한국의학물리학회지:의학물리
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• 제31권2호
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• pp.20-28
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• 2020

Purpose: The objective of this study is to perform Postal dosimetry audits for medical linear accelerators in radiation therapy institutions using glass dosimeters and Gafchromic film reading systems and postal dosimetry audit procedures, and to evaluate radiation therapy doses and mechanical accuracy in medical institutions. Methods: Photon output measured and analyzed using a standard phantom for measuring photon output dose using a glass dosimeter for medical linear accelerators. Mechanical accuracy was measured and analyzed using software for film measurement. Results: Measurement and analysis of photon beam output dose using a standard phantom glass dosimeter for photon beam output dose measurement was completed. All tolerance doses were within 5%. Mechanical accuracy measurement and analysis using a standard phantom for verifying the mechanical accuracy of linear accelerator (LINAC) using a Gafchromic film were completed, and all results were shown within tolerances (2 mm or less). Conclusions: In this study, Postal dosimetry audits were performed on the output dose and mechanical accuracy of photon beams (207 beams) for 106 LINACs from 48 institutions. As a result of corrective action and re-execution, it was confirmed that all engines met the acceptable standard within 2 mm in the linear accelerator.

• 한국의학물리학회지:의학물리
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• 제32권4호
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• pp.122-129
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• 2021

Purpose: This study aimed to design a multipurpose dose verification phantom for external audits to secure safe and optimal radiation therapy. Methods: In this study, we used International Atomic Energy Agency (IAEA) LiF powder thermoluminescence dosimeter (TLD), which is generally used in the therapeutic radiation dose assurance project. The newly designed multipurpose phantom (MPP) consists of a container filled with water, a TLD holder, and two water-pressing covers. The size of the phantom was designed to be sufficient (30×30×30 cm³). The water container was filled with water and pressed with the cover for normal incidence to be fixed. The surface of the MPP was devised to maintain the same distance from the source at all times, even in the case of oblique incidence regardless of the water level. The MPP was irradiated with 6, 10, and 15 MV photon beams from Varian Linear Accelerator and measured by a 1.25 cm³ ionization chamber to get the correction factors. Monte Carlo (MC) simulation was also used to compare the measurements. Results: The result obtained by MC had a relatively high uncertainty of 1% at the dosimetry point, but it showed a correction factor value of 1.3% at the 5 cm point. The energy dependence was large at 6 MV and small at 15 MV. Various dosimetric parameters for external audits can be performed within an hour. Conclusions: The results allow an objective comparison of the quality assurance (QA) of individual hospitals. Therefore, this can be employed for external audits or QA systems in radiation therapy institutions.

• Journal of Radiation Protection and Research
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• 제36권3호
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• pp.154-159
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• 2011

국내 원전에서는 고 방사선량율 또는 고피폭 예상 방사선작업에 종사자의 가슴과 등에 두 개의 개인선량계를 패용하여 피폭방사선량을 평가하고 있다. 이러한 Two-Dosimeter Algorithm (TDA)으로 현장시험과 심층검토를 통해 NCRP(55:50) TDA를 최적 알고리즘으로 최종적으로 선정하였고, 2006년 이후 원전 종사자의 피폭방사선량 평가 실무에 적용 중에 있다. 한편, 2007년 국제방사선방호위원회(ICRP)는 간행물 ICRP 103을 통해 방사선가중계수 및 조직가중계수와 기준 인체모형팬텀(Reference phantom) 등을 일부 변경한 유효선량 평가방법을 제시하였다. 이에 따라 본 논문에서는 국내원전에서 적용되고 있는 NCRP (55:50) TDA에 대해 ICRP 103 방사선방호 체계 하에서의 계속 적용 타당성을 분석하였다. 그 결과, NCRP (55:50) TDA를 계속 사용하더라도 ICRP 103의 유효선량을 신뢰성 있게 평가할 수 있는 것으로 판단되었다.

• 대한방사선기술학회지:방사선기술과학
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• 제36권2호
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• pp.165-173
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• 2013

본 연구는 몬테카를로 시뮬레이션을 이용하여 양성자 빔을 피사체에 조사했을 때 발생되는 양성자, 즉발감마선 그리고 양성자 유발 중성자의 3차원적 공간분포를 polymer gel 선량계를 통해 구하고, 이를 물 팬텀에서 조사한 결과와 비교하여 3차원적 선량 분포의 정확성에 대해 알아보고자 한다. 본 연구에서 사용 된 polymer gel 선량계는 Gelatin, Methacrylic acid, Hydroquinone, Tetrakis 그리고 증류수로 이루어진 혼합물로 그 밀도는 $1.04g/cm^3$으로 물의 밀도인 $0.9998g/cm^3$과 유사하다. 본 시뮬레이션에서는 72 MeV, 116 MeV, 140 MeV 의 양성자 빔이 사용되었다. 양성자 빔은 팬텀의 핵과 반응을 하고 양성자 빔으로 인해 여기된 핵이 다시 안정하게 되기 위해 즉발감마선 그리고 양성자 유발 중성자를 방출한다. 양성자와 즉발감마선 그리고 양성자 유발 중성자는 polymer gel 선량계와 물 팬텀에서 각각 검출하였다. 3차원적 선량 분포를 얻기 위한 검출 간격은 2 mm로 하여 선량 분포를 획득하였다. Polymer gel 선량계에서의 양성자의 Bragg-peak를 구해 본 결과 Bragg-peak 지점이 물 팬텀에서의 경우와 유사하게 나타남을 확인 할 수 있었다. 72 MeV, 116 MeV, 그리고 140 MeV의 양성자 빔을 polymer gel 그리고 물 팬텀에 조사했을 때 그 내부에서의 양성자 그리고 즉발감마선의 선량 분포는 polymer gel, 물 팬텀 각각 유사한 선량분포를 가짐을 감마 인덱스 평가로 확인 할 수 있었다. 하지만 양성자 유발 중성자의 경우 물 팬텀에서는 검출이 된 반면 polymer gel 선량계에서는 검출이 되지 않았다. Polymer Gel 선량계는 3차원적 선량 분포를 얻는데 유용한 선량계이지만 양성자 조사 시 그 유발 중성자의 검출에는 한계를 보임을 확인할 수 있었다.

• Journal of Radiation Protection and Research
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• 제41권3호
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• pp.222-228
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• 2016

Background: We are developing a small size dosimeter for dose estimation in particle therapies. The developed dosimeter is an optical fiber based dosimeter mounting an radiation induced luminescence material, such as an OSL or a scintillator, at a tip. These materials generally suffer from the quenching effect under high LET particle irradiation. Materials and Methods: We fabricated two types of the small size dosimeters. They used an OSL material Eu:BaFBr and a BGO scintillator. Carbon ions were irradiated into the fabricated dosimeters at Heavy Ion Medical Accelerator in Chiba (HIMAC). The small size dosimeters were set behind the water equivalent acrylic phantom. Bragg peak was observed by changing the phantom thickness. An ion chamber was also placed near the small size dosimeters as a reference. Results and Discussion: Eu:BaFBr and BGO dosimeters showed a Bragg peak at the same thickness as the ion chamber. Under high LET particle irradiation, the response of the luminescence-based small size dosimeters deteriorated compared with that of the ion chamber due to the quenching effect. We confirmed the luminescence efficiency of Eu:BaFBr and BGO decrease with the LET. The reduction coefficient of luminescence efficiency was different between the BGO and the Eu:BaFBr. The LET can be determined from the luminescence ratio between Eu:BaFBr and BGO, and the dosimeter response can be corrected. Conclusion: We evaluated the LET dependence of the luminescence efficiency of the BGO and Eu:BaFBr as the quenching effect. We propose and discuss the correction of the quenching effect using the signal intensity ratio of the both materials. Although the correction precision is not sufficient, feasibility of the proposed correction method is proved through basic experiments.

• International Journal of Contents
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• 제8권2호
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• pp.52-59
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• 2012

This study uses digital imaging and communications in medicine (DICOM) files acquired after CT scan to obtain the absorbed dose distribution inside the body by using the patient's actual anatomical data; uses geometry and tracking (Geant)4 as a way to obtain the accurate absorbed dose distribution inside the body. This method is easier to establish the radioprotection plan through estimating the absorbed dose distribution inside the body compared to the evaluation of absorbed dose using thermo-luminescence dosimeter (TLD) with inferior reliability and accuracy because many variables act on result values with respect to the evaluation of the patient's absorbed dose distribution in diagnostic imaging and the evaluation of absorbed dose using phantom; can contribute to improving reliability accuracy and reproducibility; it makes significance in that it can implement the actual patient's absorbed dose distribution, not just mere estimation using mathematical phantom or humanoid phantom. When comparing the absorbed dose in polymethly methacrylate (PMMA) phantom measured in metal oxide semiconductor field effect transistor (MOSFET) dosimeter for verification of Geant4 and the result of Geant4 simulation, there was $0.46{\pm}4.69%$ ($15{\times}15cm^2$), and $-0.75{\pm}5.19%$ ($20{\times}20cm^2$) difference according to the depth. This study, through the simulation by means of Geant4, suggests a new way to calculate the actual dose of radiation exposure of patients through DICOM interface.

• Journal of Radiation Protection and Research
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• 제48권4호
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• pp.197-203
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• 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.

• Journal of Radiation Protection and Research
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• 제16권1호
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• pp.25-32
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• 1991

MCNP 코드를 사용하여 LAEA에서 권고하고 있는 물팬톰과 미국내 선량계 성능시험 프로그램에서 규정하고 있는 PMMA 펜톰내 0.07mm 및 10mm 깊이에서의 환산인자 H(d)/Ka을 계산하였다. 계산은 팬톰의 한면에 수직으로 입사하는 단일에너지 광자의 확장정열범에 대해 수행하였다. 결과는 팬톰내에서 정의되는 선량당량으로 선량계를 교정할 때 환산인자로 사용될 수 있다.