• Progress in Medical Physics
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• v.16 no.2
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• pp.82-88
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• 2005

In this study, the physical compensator made with the high density material, Cerrobend, and the electronic compensator realized by the movement of a dynamic multileaf collimator were analyzed in order to verify the properness of a design function in the commercial RTP (radiation treatment planning) system, Eclipse. The CT images of a phantom composed of the regions of five different thickness were acquired and the proper compensator which can make homogeneous dose distribution at the reference depth was designed in the RTP. The frame for the casting of Cerrobend compensator was made with a computerized automatic styrofoam cutting device and the Millennium MLC-120 was used for the electronic compensator. All the dose values and isodose distributions were measured with a radiographic EDR2 film. The deviation of a dose distribution was $\pm0.99 cGy\;and\;\pm1.82cGy$ in each case of a Cerrobend compensator and a electronic compensator compared with a $\pm13.93 cGy$ deviation in an open beam condition. Which showed the proper function of the designed compensators in the view point of a homogeneous dose distribution. When the absolute dose value was analyzed, the Cerrobend compensator showed a $+3.83\%$ error and the electronic compensator showed a $-4.37\%$ error in comparison with a dose value which was calculated in the RTP. These errors can be admtted as an reasonable results that approve the accuracy of the compensator design in the RTP considering the error in the process of the manufacturing of the Cerrobend compensator and the limitation of a film in the absolute dosimetry.

• Radiation Oncology Journal
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• v.27 no.2
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• pp.91-102
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• 2009

Purpose: To compare the accuracy and efficacy of EDR2 film, a 2D ionization chamber array (MatriXX) and an amorphous silicon electronic portal imaging device (EPID) in the pre-treatment QA of IMRT. Materials and Methods: Fluence patterns, shaped as a wedge with 10 steps (segments) by a multi-leaf collimator (MLC), of reference and test IMRT fields were measured using EDR2 film, the MatriXX, and EPID. Test fields were designed to simulate leaf positioning errors. The absolute dose at a point in each step of the reference fields was measured in a water phantom with an ionization chamber and was compared to the dose obtained with the use of EDR2 film, the MatriXX and EPID. For qualitative analysis, all measured fluence patterns of both reference and test fields were compared with calculated dose maps from a radiation treatment planning system (Pinnacle, Philips, USA) using profiles and $\gamma$ evaluation with 3%/3 mm and 2%/2 mm criteria. By measurement of the time to perform QA, we compared the workload of EDR2 film, the MatriXX and EPID. Results: The percent absolute dose difference between the measured and ionization chamber dose was within 1% for the EPID, 2% for the MatriXX and 3% for EDR2 film. The percentage of pixels with $\gamma$%>1 for the 3%/3 mm and 2%/2 mm criteria was within 2% for use of both EDR2 film and the EPID. However, differences for the use of the MatriXX were seen with a maximum difference as great as 5.94% with the 2%/2 mm criteria. For the test fields, EDR2 film and EPID could detect leaf-positioning errors on the order of -3 mm and -2 mm, respectively. However it was difficult to differentiate leaf-positioning errors with the MatriXX due to its poor resolution. The approximate time to perform QA was 110 minutes for the use of EDR2 film, 80 minutes for the use of the MatriXX and approximately 55 minutes for the use of the EPID. Conclusion: This study has evaluated the accuracy and efficacy of EDR2 film, the MatriXX and EPID in the pre-treatment verification of IMRT. EDR2 film and the EPID showed better performance for accuracy, while the use of the MatriXX significantly reduced measurement and analysis times. We propose practical and useful methods to establish an effective QA system in a clinical environment.

• Progress in Medical Physics
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• v.19 no.4
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• pp.305-312
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• 2008

The aim of this study is to introduce the accuracy of Ir-192 source's apparent activity using the well-type chamber and the Farmer-type ionization chamber in the high dose rate brachytherapy. We measured the apparent activity of Ir-192 that each medical center in the country has and the apparent activity of calibration certificate provided by manufacturer is compared with that by our experimental measurement. The number of sources used for the activity comparison was 5. The accuracy of the measured activity was in the range of -2.8% to -1.0% and -2.1% to 0.2% for the Farmer-type chamber system (Jig) and for the well-type, respectively. The maximum difference was within 1.0% for comparison with two calibration's tool. Our results demonstrate that well-type chamber as wall as Farmer-type chamber is a appropriate system as the routine source calibration procedures in HDR brachytherapy. Whenever a new source is installed to use in clinics, by periods, a source calibration should be carried out.

• Proceedings of the Korean Society of Medical Physics Conference
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• 2003.09a
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• pp.70-70
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• 2003

경피적관상동맥성형술(CPTCA)이나 스텐트삽입술 후에 발생하는 재협착을 방지하기 위한 방사선을 조사하는 방법 중에 베타 입자를 방출하는 액체 선원을 catheter풍선 내에 넣어 일정 시간 방사선 조사 시키는 방법이 있다. 조사시킬 혈관의 길이가 길어 한번의 방사선 조사가 어려울 경우 영역을 분할하여 두 번에 나누어 조사할 경우가 있다. 조사영역의 겹치는 부근의 흡수선량이 고선량이나 저선량이 되는가를 알기 위하여 두 풍선간의 접근 거리에 따른 혈관내벽의 흡수선량 분포를 알아보았다. 풍선내의 액체 선원은 Ho-l66을 이용하였고 Ho-l66의 물리적 반감기는 26.8시간이고 최대에너지 1.85 MeV, 평균에너지 0.69 MeV와 최대에너지 1.77 MeV, 평균에너지 0.65 MeV를 갖는 베타 입자를 방출한다. Ho-l66 의 방사선 흡수선량을 측정하기 위하여 GafChromic 필름(Nuclear Associates, Carle Place, NY, USA)을 이용하였고, 방사선이 조사된 필름의 optical density는 videodensitometer(Wellhofer, Schwarzen-bruck, Germany)를 이용하여 값을 읽었다. Catheter 풍선은 직경이 3 mm 이고 길이가 20 mm인 것을 이용하였다. 혈관 내벽의 최대 흡수선량을 표준화하여 겹치는 부분의 흡수선량 분포를 접근 거리에 따라 구하였다. 또한 몬테카를로 시abf레이션으로 확인하였다. 두 풍선의 겹치는 부근의 선량 분포는 풍선 중앙에서 중앙사이의 거리가 21 mm 일 때 중앙에서 20% 증가하였고, 거리가 22 mm일 때와 23 mm일 때 각각 10%와 40%의 감소를 보였다. 풍선 도자의 풍선 안에 베타입자 방출 액체 선원을 넣어 혈관내벽에 방사선 조사하는 방법은 비정거리가 짧아 혈관 내벽 부근에만 방사선을 조사시키고 그 외 중요 장기에는 영향을 덜 미치는 장점이 있다. 그러나 혈관 내벽 표면으로 부터의 거리에 따라 흡수선량이 급격히 떨어지는 분포를 이루기 때문에 두 개의 풍선이 겹치는 부근의 흡수선량은 아주 작은 접근 거리에서도 급격한 변화를 보였다. 따라서 시술 중에 겹치는 부분을 아주 적게 분할하여 정확하게 차례차례로 조사시키기 위해서는 신중한 거리 조정을 하여야 한다.

• Progress in Medical Physics
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• v.6 no.1
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• pp.13-18
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• 1995

Dose distribution of HDR-RALS source represents an inverse square law as the distance. Difference of measurement value and calculation value according of brachytherapy. Therefore, in HDR-RALS dose calibration and calculation have an important effect in treatment of uterine cervical cancer and absorbed dose of interesting points. In intracavitary therapy, particula attention is paid for precise determination of the doses to be applied. In this report, we have discussed that the calibration of a HDR-RALS, differences between calculation dose use of isodose chart and measurement in rectum. Dose rate calibration of radiation sources are obtained from air kerma and Г factor with calibraed ion chamber for cobalt source. and used semiconductor detector for compared with measurement in phantom. Eighteen patients were treated with a HDR-RALS for intrcavitarty irradiation (ICR) using a cobalt-cesium source. Repoductivity of dose measurements were 0.3 -1.1％ in phantom. The means of dose distribution was -6- ＋21％ between calculation of isodose chart and measurement of recyum, and was same mean value upper 6.3％ in measurement value than calculation does.

• Journal of Radiation Protection and Research
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• v.31 no.2
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• pp.97-104
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• 2006

In recent years, the MOSFET dosimeter has been widely used in various medical applications such as dose verification in radiation therapeutic and diagnostic applications. The MOSFET dosimeter is, however, mainly made of silicon and shows some energy dependence for low energy Photons. Therefore, the MOSFET dosimeter tends to overestimate the dose for low energy scattered photons in a phantom. This study determines the correction factors to compensate these dependences of the MOSFET dosimeter in ATOM phantom. For this, we first constructed a computational model of the ATOM phantom based on the 3D CT image data of the phantom. The voxel phantom was then implemented in a Monte Carlo simulation code and used to calculate the energy spectrum of the photon field at each of the MOSFET dosimeter locations in the phantom. Finally, the correction factors were calculated based on the energy spectrum of the photon field at the dosimeter locations and the pre-determined energy and directional dependence of the MOSFET dosimeter. Our result for $^{60}Co$ and $^{137}Cs$ photon fields shows that the correction factors are distributed within the range of 0.89 and 0.97 considering all the MOSFET dosimeter locations in the phantom.

• Progress in Medical Physics
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• v.25 no.4
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• pp.233-241
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• 2014

The aim of this study is to develop a new software tool for 3D dose verification using $PRESAGE^{REU}$ Gel dosimeter. The tool included following functions: importing 3D doses from treatment planning systems (TPS), importing 3D optical density (OD), converting ODs to doses, 3D registration between two volumetric data by translational and rotational transformations, and evaluation with 3D gamma index. To acquire correlation between ODs and doses, CT images of a $PRESAGE^{REU}$ Gel with cylindrical shape was acquired, and a volumetric modulated arc therapy (VMAT) plan was designed to give radiation doses from 1 Gy to 6 Gy to six disk-shaped virtual targets along z-axis. After the VMAT plan was delivered to the targets, 3D OD data were reconstructed from 512 projection data from $Vista^{TM}$ optical CT scanner (Modus Medical Devices Inc, Canada) per every 2 hours after irradiation. A curve for converting ODs to doses was derived by comparing TPS dose profile to OD profile along z-axis, and the 3D OD data were converted to the absorbed doses using the curve. Supra-linearity was observed between doses and ODs, and the ODs were decayed about 60% per 24 hours depending on their magnitudes. Measured doses from the $PRESAGE^{REU}$ Gel were well agreed with the TPS doses at central region, but large under-doses were observed at peripheral region at the cylindrical geometry. Gamma passing rate for 3D doses was 70.36% under the gamma criteria of 3% of dose difference and 3 mm of distance to agreement. The low passing rate was resulted from the mismatching of the refractive index between the PRESAGE gel and oil bath in the optical CT scanner. In conclusion, the developed software was useful for 3D dose verification from PRESAGE gel dosimetry, but further improvement of the Gel dosimetry system were required.

• Journal of the Korean Society of Radiology
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• v.9 no.5
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• pp.287-293
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• 2015

Because of esophageal cancer has the long length of the lesion and also inhomogeneous in depth. So, the radiation dose distribution was inhomogeneous in radiation therapy. To overcomes the dose distribution uniformity using half beam method. Patient's CT image was used radiation treatment planning. We used two planning methods that one is the using normal beam and another is using half beam. Than comparing the two radiotherapy planning using target coverage, dose volume histogram, conformity index, homogeneity index and normal tissues - heart, spinal cord, lung -. In results, Treatment planning using half beam is little more than normal beam in target coverage, dose volume histogram, conformity index, homogeneity index and normal tissues covering. However, If the patient is not correct position patients may arise a side effect. Thus, the using in Half beam involving the geometrically exact under lung cancer is considered to advantage.

• Proceedings of the Korean Society of Medical Physics Conference
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• 2003.09a
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• pp.58-58
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• 2003

목적 : 본 연구에서는 C-arm과 CT에 사용 가능한 자궁경부암용 팬톰을 개발하고 이를 이용하여 기존의 필름 방법에 기반한 위치 확인 방법과 CT 재구성 방법의 정확성을 비교 연구하고자 한다. 정확성이 검증된 후에는 두 방법의 장점을 이용하기 위해 CT로 재구성된 좌표를 필름의 좌표로 변환시켜 현재 사용되고 있는 필름에 기반한 근접 치료 계획 시행에 도움을 주고자 한다. 방법 : 자체 제작한 자궁경부암용 팬톰은 인체 등가 물질인 물과 아크릴을 사용하였고, 크게 localizer 부분과 팬톰 부분으로 구성되어 있다. 또한, 실제 자궁경부암 환자의 임상적인 구조를 모사하여 제작하였다. 자궁경부암 치료시 중요 장기인 방광과 직장을 구와 원기둥으로 설계하였고, 고선량율 applicator는 아크릴 판의 흠으로 고정시켜 제작하였기 때문에 CT 촬영시 applicator를 제거한 영상에서도 applicator의 구조가 정확하게 묘사될 수 있도록 제작하였다. 두 시스템에서 재구성된 좌표를 비교하기 위해 각각의 시스템에서의 얻은 재구성 좌표와 팬톰 자체의 localizer와 재구성 알고리즘을 바탕으로 개발된 프로그램을 이용하여 얻은 좌표로 두 재구성 좌표의 비교 연구를 수행하였다. 정확성이 검증되고 장기의 정보가 담긴 CT의 좌표는 자체 개발된 프로그램으로 2 차원의 필름 좌표로 변환되었다. 본 연구에 사용된 모든 프로그램은 ILD 5.5를 사용하여 개발되었다. 결과 : 두 시스템의 좌표 비교 결과 x, y 축은 차이가 2mm 이내로 비교적 정확한 실험 결과를 얻을 수 있었고, z 축의 경우 CT 슬라이드의 굵기에 따라 2mm-3mm 이내의 차이가 있음을 관찰할 수 있었다. z 축을 제외한 좌표의 차이는 획득한 영상에서 컴퓨터로 좌표를 옮기는 localizer 좌표 선택 과정에 발생했을 것으로 예상된다. 또한, 이 검증된 좌표와 개발된 프로그램을 이용하여 우리는 CT의 좌표를 2차원의 필름 좌표로 정확하게 변환할 수 있었다. 결론 : 이 연구로부터 기존의 C-arm 재구성 방법과 CT 재구성 방법의 비교를 통해 각 치료 기기의 신뢰성을 직접 확인할 수 있었으며, 비교를 통해 검증된 CT의 좌표를 필름 좌표로 변환시킴으로서, 각 시스템의 장점만을 결합한 효과적인 치료 계획을 세울 수 있는 가능성을 제시하였다. 또한 물과 아크릴을 사용한 비교적 간단하고 경제적인 방법으로 C-arm, CT 그리고 MRI에 모두 이용 가능한 팬톰을 제작하여 쉽고 정확하게 위치를 확인할 수 있었다. 더 나아가, 본 연구에서 제작된 자궁경부암 팬톰은 근접치료를 포함하여 관련 팬톰 개발에 도움을 줄 수 있을 것으로 예상된다.

• Journal of the Korean Society of Radiology
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• v.15 no.6
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• pp.795-801
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• 2021

The designed drone-based unmanned remote radiation detection module was developed according to the needs of the nuclear power plant decommissioning workshop. Using the Geiger-Mueller tube sensitive to low-level radiation measurement, It was manufactured to measure the amount of radiation leaking into and out of the containment vessel. The drone-based radiation detection module weighs less than 200g, It can be operated inside and outside the containment vessel of a nuclear power plant. To check the performance of the designed equipment, a performance evaluation test was conducted with reference to the international standard (IEC-60864). The stability of the radiation detection module designed to meet the needs of the field the statistical rate of change by repeated measurements in the rate of change experiment to evaluate the measurement accuracy was ±4.6%. The accuracy ±7.3% in the linearity experiment to evaluate the dose rate dependence, the linear The figure satisfies the international performance evaluation standard of ±3.5%. The radiation detection module developed in this study is a customized equipment for a nuclear power plant dismantling workshop. It will be helpful for accurate measurement of space dose rate and safety management of radiation worksites in sites with a lot of radiation dust.