• 한국의학물리학회지:의학물리
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• 제28권3호
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• pp.111-121
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• 2017

Verification of dose distribution is an essential part of ensuring the treatment planning system's (TPS) calculated dose will achieve the desired outcome in radiation therapy. Each measurement have uncertainty associated with it. It is desirable to reduce the measurement uncertainty. A best approach is to reduce the uncertainty associated with each step of the process to keep the total uncertainty under acceptable limits. Point dose patient specific quality assurance (QA) is recommended by American Association of Medical Physicists (AAPM) and European Society for Radiotherapy and Oncology (ESTRO) for all the complex radiation therapy treatment techniques. Relative and absolute point dose measurement methods are used to verify the TPS computed dose. Relative and absolute point dose measurement techniques have a number of steps to measure the point dose which includes chamber cross calibration, electrometer reading, chamber calibration coefficient, beam quality correction factor, reference conditions, influences quantities, machine stability, nominal calibration factor (for relative method) and absolute dose calibration of machine. Keeping these parameters in mind, the estimated relative percentage uncertainty associated with the absolute point dose measurement is 2.1% (k=1). On the other hand, the relative percentage uncertainty associated with the relative point dose verification method is estimated to 1.0% (k=1). To compare both point dose measurement methods, 13 head and neck (H&N) IMRT patients were selected. A point dose for each patient was measured with both methods. The average percentage difference between TPS computed dose and measured absolute relative point dose was 1.4% and 1% respectively. The results of this comparative study show that while choosing the relative or absolute point dose measurement technique, both techniques can produce similar results for H&N IMRT treatment plans. There is no statistically significant difference between both point dose verification methods based upon the t-test for comparing two means.

• 대한방사선치료학회지
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• 제24권2호
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• pp.61-66
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• 2012

목 적: 본 연구에서는 자궁강 내 근접치료 시 ABS (American Brachytherapy Society)에서 권고한 H점(point H)을 이용한 치료계획을 수립해 보았고, 이를 A점(point A)에 처방한 치료계획과 비교하고자 한다. 대상 및 방법: 2010년 3월부터 2012년 1월까지 본원에 내원한 자궁경부암 환자 중 탄뎀(tandem)과 난형체(ovoid)를 이용해 고선량률 강내 근접치료(high dose rate intracavitary brachytherapy)를 시행한 103명을 대상으로 하였다. 치료계획은 Manchester System에 따라 A점, 방광 기준점, 직장 기준점을 지정하였고, ABS의 권고에 따라 H점을 지정하였다. 또한 임의로 S자 결장기준점과 질 기준점을 설정하였다. A점과 H점의 위치가 얼마나 차이가 나는지 살펴보았으며, H점에 100%의 선량을 처방하였을 때 A점에 들어가는 선량을 계산하였다. 그리고 A점과 H점에 각각 선량을 처방하였을 때 직장, 방광, S자 결장, 질 기준점에 들어가는 선량을 비교 분석하였다. 결 과: H점이 A점보다 미측에 있는 경우 A점의 상대선량은 기존의 A점이 아닌 H점에 처방하였을 때 더 적어지는 경향을 보였다. 방광 기준점과 직장 기준점, S자결장 기준점, 질 기준점에서의 상대선량은 H점이 두측에 있는 경우 H점에 처방하였을때의 선량이 A점에 처방하였을 때보다 크며, 미측에 있는 경우 더 적어지는 양상을 보였다. 결 론: H점이 A점보다 두측에 위치할수록 주변 장기의 흡수선량이 커지고, 미측에 위치할수록 주변 장기의 흡수선량이 적어지는 경향을 보였다. 그 선량 차이가 치료에 큰 영향을 미칠 정도는 아니지만, 두 치료계획에서의 선량 분포 및 주변 장기 흡수선량 차이가 크다면 두 점의 치료계획은 비교 또는 참고할 만한 가치가 있는 것으로 생각된다.

• 방사선산업학회지
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• 제17권3호
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• pp.275-282
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• 2023

Workers in nuclear power plants are likely to be exposed to radiation from various geometrical sources. In order to evaluate the exposure level, the point-kernel method can be utilized. In order to perform a dose assessment based on this method, the radiation source should be divided into point sources, and the number of divisions should be set by the evaluator. However, for the general public, there may be difficulties in selecting the appropriate number of divisions and performing an evaluation. Therefore, the purpose of this study is to develop an algorithm for dose assessment for arbitrary shaped sources based on the point-kernel method. For this purpose, the point-kernel method was analyzed and the main factors for the dose assessment were selected. Subsequently, based on the analyzed methodology, a dose assessment algorithm for arbitrary shaped sources was developed. Lastly, the developed algorithm was verified using Microshield. The dose assessment procedure of the developed algorithm consisted of 1) boundary space setting step, 2) source grid division step, 3) the set of point sources generation step, and 4) dose assessment step. In the boundary space setting step, the boundaries of the space occupied by the sources are set. In the grid division step, the boundary space is divided into several grids. In the set of point sources generation step, the coordinates of the point sources are set by considering the proportion of sources occupying each grid. Finally, in the dose assessment step, the results of the dose assessments for each point source are summed up to derive the dose rate. In order to verify the developed algorithm, the exposure scenario was established based on the standard exposure scenario presented by the American National Standards Institute. The results of the evaluation with the developed algorithm and Microshield were compare. The results of the evaluation with the developed algorithm showed a range of 1.99×10^-1~9.74×10^-1 μSv hr^-1, depending on the distance and the error between the results of the developed algorithm and Microshield was about 0.48~6.93%. The error was attributed to the difference in the number of point sources and point source distribution between the developed algorithm and the Microshield. The results of this study can be utilized for external exposure radiation dose assessments based on the point-kernel method.

• Radiation Oncology Journal
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• 제12권3호
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• pp.387-392
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• 1994

Purpose : This study was done to confirm the reference point variation according to variation in applicator configuration in each fractioation of HDR ICR. Materials and Methods : We analyzed the treatment planning of HDRICR for 33 uterine cervical cancer patients treated in department of therapeutic radiology from January 1992 to February 1992. Analysis was done with respect to three view points-Interfractionation A point variation, interfractionation bladder and rectum dose ratio variation, interfractionation treatment volume variation. Interfractionation A point variation was defined as difference between maximum and minimum distance from fixed rectal point to A point in each patient. Interfractionation bladder and rectum dose ratio variation was defined as difference between maximum and minimum dose ratio of bladder or rectum to A point dose in each patient, Interfractionation treatment volume variation was defined as difference between miximum and minimum treatment volume which absorbed over the described dose-that is, 350 cGy or 400 cGy-in each patient. Results The mean of distance from rectum to A point was 4.44cm, and the mean of interfractionation distance variation was 1.14 cm in right side,1.09 cm in left side. The mean of bladder and rectum dose ratio was $63.8\%$ and $63.1\%$ and the mean of interfractionation variation was $14.9\%$ and $15.8\%$ respectively. With fixed planning administration of same planning to all fractionations as in first fractionation planning-mean of bladder and rectum dose ratio was $64.9\%$ and $72.3\%$.and the mean of interfraction variation was $28.1\%$ and $48.1\%$ reapectively. The mean of treatment volume was $84.15cm^3$ and the interfractionation variation was $21.47cm^2$. Conclusion : From these data, it was confirmed that there should be adapted planning for every fractionation ,and that confirmation device installed in ICR room would reduce the interfractionation variation due to more stable applicator configuration.

• Asian Pacific Journal of Cancer Prevention
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• 제15권13호
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• pp.5259-5264
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• 2014

Background: CT based brachytherapy allows 3-dimensional (3D) assessment of organs at risk (OAR) doses with dose volume histograms (DVHs). The purpose of this study was to compare computed tomography (CT) based volumetric calculations and International Commission on Radiation Units and Measurements (ICRU) reference-point estimates of radiation doses to the bladder and rectum in patients with carcinoma of the cervix treated with high-dose-rate (HDR) intracavitary brachytherapy (ICBT). Materials and Methods: Between March 2011 and May 2012, 20 patients were treated with 55 fractions of brachytherapy using tandem and ovoids and underwent post-implant CT scans. The external beam radiotherapy (EBRT) dose was 48.6Gy in 27 fractions. HDR brachytherapy was delivered to a dose of 21 Gy in three fractions. The ICRU bladder and rectum point doses along with 4 additional rectal points were recorded. The maximum dose ($D_{Max}$) to rectum was the highest recorded dose at one of these five points. Using the HDRplus 2.6 brachyhtherapy treatment planning system, the bladder and rectum were retrospectively contoured on the 55 CT datasets. The DVHs for rectum and bladder were calculated and the minimum doses to the highest irradiated 2cc area of rectum and bladder were recorded ($D_{2cc}$) for all individual fractions. The mean $D_{2cc}$ of rectum was compared to the means of ICRU rectal point and rectal $D_{Max}$ using the Student's t-test. The mean $D_{2cc}$ of bladder was compared with the mean ICRU bladder point using the same statistical test. The total dose, combining EBRT and HDR brachytherapy, were biologically normalized to the conventional 2 Gy/fraction using the linear-quadratic model. (${\alpha}/{\beta}$ value of 10 Gy for target, 3 Gy for organs at risk). Results: The total prescribed dose was $77.5Gy{\alpha}/{\beta}10$. The mean dose to the rectum was $4.58{\pm}1.22Gy$ for $D_{2cc}$, $3.76{\pm}0.65Gy$ at $D_{ICRU}$ and $4.75{\pm}1.01Gy$ at $D_{Max}$. The mean rectal $D_{2cc}$ dose differed significantly from the mean dose calculated at the ICRU reference point (p<0.005); the mean difference was 0.82 Gy (0.48-1.19Gy). The mean EQD2 was $68.52{\pm}7.24Gy_{{\alpha}/{\beta}3}$ for $D_{2cc}$, $61.71{\pm}2.77Gy_{{\alpha}/{\beta}3}$ at $D_{ICRU}$ and $69.24{\pm}6.02Gy_{{\alpha}/{\beta}3}$ at $D_{Max}$. The mean ratio of $D_{2cc}$ rectum to $D_{ICRU}$ rectum was 1.25 and the mean ratio of $D_{2cc}$ rectum to $D_{Max}$ rectum was 0.98 for all individual fractions. The mean dose to the bladder was $6.00{\pm}1.90Gy$ for $D_{2cc}$ and $5.10{\pm}2.03Gy$ at $D_{ICRU}$. However, the mean $D_{2cc}$ dose did not differ significantly from the mean dose calculated at the ICRU reference point (p=0.307); the mean difference was 0.90 Gy (0.49-1.25Gy). The mean EQD2 was $81.85{\pm}13.03Gy_{{\alpha}/{\beta}3}$ for $D_{2cc}$ and $74.11{\pm}19.39Gy_{{\alpha}/{\beta}3}$ at $D_{ICRU}$. The mean ratio of $D_{2cc}$ bladder to $D_{ICRU}$ bladder was 1.24. In the majority of applications, the maximum dose point was not the ICRU point. On average, the rectum received 77% and bladder received 92% of the prescribed dose. Conclusions: OARs doses assessed by DVH criteria were higher than ICRU point doses. Our data suggest that the estimated dose to the ICRU bladder point may be a reasonable surrogate for the $D_{2cc}$ and rectal $D_{Max}$ for $D_{2cc}$. However, the dose to the ICRU rectal point does not appear to be a reasonable surrogate for the $D_{2cc}$.

• Nuclear Engineering and Technology
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• 제55권6호
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• pp.1966-1973
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• 2023

Virtual reality technology has been widely used in the field of nuclear and radiation safety, dose rate computing in virtual environment is essential for optimizing radiation protection and planning the work in radioactive-controlled area. Because the CPU-based gamma dose rate computing takes up a large amount of time and computing power for voxelization of volumetric radioactive source, it is inefficient and limited in its applied scope. This study is to develop an efficient gamma dose rate computing code and apply into fast virtual simulation. To improve the computing efficiency of the point kernel algorithm in the reference (Li et al., 2020), we design a GPU-based computing framework for taking full advantage of computing power of virtual engine, propose a novel voxelization algorithm of volumetric radioactive source. According to the framework, we develop the GPPK(GPU-based point kernel gamma dose rate computing) code using GPU programming, to realize the fast dose rate computing in virtual world. The test results show that the GPPK code is play and plug for different scenarios of virtual simulation, has a better performance than CPU-based gamma dose rate computing code, especially on the voxelization of three-dimensional (3D) model. The accuracy of dose rates from the proposed method is in the acceptable range.

• 대한방사선치료학회지
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• 제33권
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• pp.145-153
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• 2021

목 적: 본 연구에서는 가임기 여성의 유방암 방사선 치료 시 난소 선량에 대해 실험을 통하여 평가해보고자 한다. 치료기법에 따른 치료계획시스템에서 계산된 선량과 열형광선량계를 이용한 측정선량을 비교·분석하여 난소 선량을 평가하고 납(Pb) 앞치마의 사용유무에 따른 선량 분석을 통해 임상에서의 유용성을 알아보고자 한다. 대상 및 방법: 측정에는 Rando humanoid phantom을 이용하였고, 치료기법으로는 쐐기필터치료기법, 3차원 입체조형치료, 세기변조방사선치료를 사용하였다. CT simulator를 이용하여 얻은 Rando humanoid phantom 3D 영상의 우측 유방에 처방선량의 95%가 전달될 수 있도록 치료계획을 세웠고, TLD를 Rando hunmanoid phantom의 가상 표적의 표면 및 심부에 삽입하고 방사선을 조사하였다. 측정위치는 치료 중심점과 Rando humanoid phantom의 정중앙을 중심으로 반대쪽 유방으로 2cm 이동한 지점과 치료 중심축 및 하방으로 우측 유방의 경계면에서 5cm, 10cm, 12.5cm, 15cm, 17.5cm, 20cm, 우측 난소 위치의 표면과 중심점을 포함하여 총 9개 지점에서 측정하였다. 치료계획시스템의 선량 비교에서는 쐐기필터치료기법 2가지와 3차원 입체조형치료, 세기변조방사선치료 등 총 4개의 치료 계획을 수립하여 비교하였다. 그리고 TLD를 이용한 측정값 비교는 세기변조방사선치료와 쐐기필터를 이용한 치료를 비교하였고, 납 앞치마의 사용유무에 따라서 세기변조방사선치료의 선량차이를 측정하여 비교·분석하였다. 측정값은 각 포인트마다 3개의 TLD값 평균을 내고 TLD 교정값을 이용하여 환산하였으며 이를 Point dose mean값으로 계산하였다. 치료계획값과 실제 측정값을 비교하기 위해 각 지점마다 절대선량값을 측정하여 %Diff 값으로 계산하였다. 결 과: 치료 중심점인 Point A에서는 치료계획시스템에서 최대 201.7cGy가 나왔고, 실제 TLD 측정값은 최대 200.6cGy가 나왔다. 모든 치료계획시스템에서 유방 경계면으로부터 하방으로 17.5cm 떨어진 지점인 Point G 부터는 0cGy로 계산이 되었다. 실제 TLD 측정 결과 Point G에서는 최대 2.6cGy가 나왔고, 난소선량인 Point J에서는 최대 0.9cGy로 나타났으며 %Diff값은 0.3%~1.3%였다. 납 앞치마의 사용유무에 따른 선량 차이는 최대 2.1cGy에서 최소 0.1cGy로 나타났으며 %Diff값은 0.1%~1.1%였다. 결 론: 치료계획시스템에서 3가지 치료계획에 따른 선량차이는 최저 0.85%에서 최고 2.45%로 큰 격차를 보이지 않았다. 난소에서 Rando humanoid phantom의 치료계획과 실제 측정한 선량차이는 0.9% 이내로 나타났으나 실제 측정에서 조금 더 높게 측정되었다. 이는 치료계획시스템에서 산란선의 영향을 정확하게 반영하지 못하였고, 실제 측정에서는 TLD를 삽입한 상태로 CBCT를 촬영한 선량과 산란선량이 반영된 것으로 사료된다. 납 앞치마의 유무에 따른 선량측정에서 납 앞치마를 사용했을 경우에 치료범위에서 가까운 거리일수록 차폐의 효과가 있었으며, 치료범위에서 15cm 이상 거리가 있는 경우에는 거의 영향을 미치지 않는 것으로 나타났다. 임상적으로 방사선 치료 중에는 임신이나 인공수정을 하기에는 적절하지 않지만, 치료 중 난소에 조사된 선량은 방사선 치료 후 가임기 여성의 생식 기능에 크게 영향을 주지 않을 것으로 생각된다. 하지만 가임 여성의 경우에는 지속적인 불안감을 가지고 있으므로 이번 결과를 통한 데이터를 제시함으로써 심리적인 안정을 도모할 수 있을 것으로 사료된다.

• Radiation Oncology Journal
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• 제2권1호
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• pp.101-106
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• 1984

Various methods are available for determination of exposure time in intracavitary radiotherapy of the carcinoma of the uterine cervix. To determine the accuracy of dose calculation with isodose curve for TAO applicator, comparison with results calculated by computer for radiotherapy treatment Planning was done in 24 procedures done in 12 consecutive patients with the carcinoma of the uterine cervix from May to December, 1983. The results are as follows: 1. The average dose rate Per hour of Point A was 87.70 rad, being 89.91 rad ana 85.49 rad in left and right, respectively. 2. The average percentage of dose rate of point A calculated by isodose curve method over that by computer was $101.28\%$ and the difference was less than $5\%$ in 17 Procedures and over $10\%$ in only 3 procedures. 3. The average percentage in case of point B was $108.67\%$. In conclusion, in most cases the difference was less than 200 rad for point A and less than 100 rad for point B during 2 courses of intracavitary radiotherapy. And so the dose rate calculation with isodose curve for TAO applicator is comparatively accurate.

• 한국의학물리학회지:의학물리
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• 제29권2호
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• pp.53-58
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• 2018

This paper evaluates patient-specific quality assurance (PSQA) in the treatment of small and multiple tumors by the CyberKnife system with fixed collimators, using an ion chamber and EBT3 films. We selected 49 patients with single or multiple brain tumors, and the treatment plans include one to four targets with total volumes ranging from 0.12 cc to 3.74 cc. All PSQA deliveries were performed with a stereotactic dose verification phantom. The A16 microchamber (Standard Imaging, WI, USA) and Gafchromic EBT3 film (Ashland ISP Advanced Materials, NJ, USA) were inserted into the phantom to measure the point dose of the target and the dose distribution, respectively. The film was scanned 1 hr after irradiation by a film digitizer scanner and analyzed using RIT software (Radiological Imaging Technology, CO, USA). The acceptance criteria was <5% for the point dose measurement and >90% gamma passing rate using 3%/3 mm and relative dose difference, respectively. The point dose errors between the calculated and measured dose by the ion chamber were in the range of -17.5% to 8.03%. The mean point dose differences for 5 mm, 7.5 mm, and 10 mm fixed cone size was -11.1%, -4.1%, and -1.5%, respectively. The mean gamma passing rates for all cases was 96.1%. Although the maximum dose distribution of multiple targets was not shown in the film, gamma distribution showed that dose verification for multiple tumors can be performed. The use of the microchamber and EBT3 film made it possible to verify the dosimetric and mechanical accuracy of small and multiple targets. In particular, the correction factors should be applied to small fixed collimators less than 10 mm.

• 한국안전학회지
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• 제24권6호
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• pp.157-162
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• 2009

Radioactive medicines are used a lot owing to the increase of a PET-CT examination using glucose metabolism useful for the early diagnosis of diseases. Therefore, the spatial dose that is generated from patients and their surroundings causes the patients' guardians and health professional to be exposed to radiation. However, they get unnecessarily exposed to radiation because medical institutions lack in space for isolation and recognition of the examination. This research intended to examine the spatial dose rates by measuring the dose emitted from the patient for 48 hours to whom F-18 FDG was administered. The spatial dose rates that were measured 100cm away from the patient's body after F-18 FDG was injected were $65.88{\mu}$Sv/hr at 60-minute point, $45.13{\mu}$Sv/hr at 90-minute point, $9.88{\mu}$Sv/hr at 6-hour point, and $1.24{\mu}$Sv/hr at 12-hour point. When the dose that the guardian and health professional got was converted into the annual(240-day working) accumulative dose, it was examined that the guardian received 81.56 mSv/yr and health professional received 49.36mSv/yr. In addition, the result has revealed that the dose that the patient received from one time of PET-CT examination was 3.75mSv/yr, which is 1.5 times more when compared with the annual natural radiation exposure dose.