• Progress in Medical Physics
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• v.11 no.2
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• pp.91-99
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• 2000

This is a preliminary study for developing the method of the dose reconstruction in the patients, irradiated by mega-voltage photon beams from the linear accelerator, using the transit dose distributions. In this study we present the method of three-dimensional dose reconstruction and evaluate the method by computer simulation. To acquire the dose distributions in the patients (or phantoms) we first calculate the differences between the doses at the arbitrary points in the patients and the doses at the corresponding points where the transit doses are measured. Then, we can get the dose in the patients from the measured transit dose and the calculated value of the difference. The dose differences are calculated by applying the inverse square law and using the linear attenuation coefficient. The scatter to primary dose ratios, which are calculated by the Monte Carlo program using the CT data of the patient (or phantoms), are also used in the calculations. For the evaluation of this method we used various kinds of homogeneous and inhomogeneous phantoms and calculated the transit dose distributions with the Monte Carlo program. From the distributions we reconstructed the dose distributions in the phantom. We used mono-energy Photon beam of 1.5MeV and Monte Carlo program EGS4. The comparison between the dose distributions reconstructed using the method and the distributions calculated by the Monte Carlo program was done. They agreed within errors of -4%∼+2%. This method can be used to predict the dose distributions in the patient

• Radiation Oncology Journal
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• v.20 no.4
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• pp.381-390
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• 2002

Purpose : To develop a dose calibration program for the IAEA TRS-277 and AAPM TG-21, based on the air kerma calibration factor (or the cavity-gas calibration factor), as well as for the IAEA TRS-398 and the AAPM TG-51, based on the absorbed dose to water calibration factor, so as to avoid the unwanted error associated with these calculation procedures. Materials and Methods : Currently, the most widely used dosimetry Protocols of high energy photon beams are the air kerma calibration factor based on the IAEA TRS-277 and the AAPM TG-21. However, this has somewhat complex formalism and limitations for the improvement of the accuracy due to uncertainties of the physical quantities. Recently, the IAEA and the AAPM published the absorbed dose to water calibration factor based, on the IAEA TRS-398 and the AAPM TG-51. The formalism and physical parameters were strictly applied to these four dose calibration programs. The tables and graphs of physical data and the information for ion chambers were numericalized for their incorporation into a database. These programs were developed user to be friendly, with the Visual $C^{++}$ language for their ease of use in a Windows environment according to the recommendation of each protocols. Results : The dose calibration programs for the high energy photon beams, developed for the four protocols, allow the input of informations about a dosimetry system, the characteristics of the beam quality, the measurement conditions and dosimetry results, to enable the minimization of any inter-user variations and errors, during the calculation procedure. Also, it was possible to compare the absorbed dose to water data of the four different protocols at a single reference points. Conclusion : Since this program expressed information in numerical and data-based forms for the physical parameter tables, graphs and of the ion chambers, the error associated with the procedures and different user could be solved. It was possible to analyze and compare the major difference for each dosimetry protocol, since the program was designed to be user friendly and to accurately calculate the correction factors and absorbed dose. It is expected that accurate dose calculations in high energy photon beams can be made by the users for selecting and performing the appropriate dosimetry protocol.

• Proceedings of the Korean Society of Medical Physics Conference
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• 2003.09a
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• pp.33-33
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• 2003

목적 : 현재 국내에서 사용되고 있는 방사선치료계획 장비는 거의 모든 방사선종양학과에서 외국 회사의 제품을 사용하고 있는 실정이다. 본 연구는 국내 기술로 개발된 3 차원 조형 방사선치료계획 장비인 Core Plan의 선량계산 알고리즘의 정확성 및 방사선 치료계획 장비로서의 유용성에 관해 평가하고 본 장비의 특징에 대해 간략히 소개하고자 한다. 재료 및 방법 : 본 연구는 2002 년 11 월에 가톨릭대학교 성모병원 방사선종양학과와 서울씨앤제이의 연구계약에 의해 시행되었다. 본 장비에 대한 평가는 방사선분포 및 계산상의 정확성과 임상적용시의 유용성의 관점에서 시행되었다. 본 장비에서 이용된 광자선 선량계산은 Clarkson-Cunningham 모델이며 전자선 선량계산은 2.5D Hogstrom 알고리즘이다. 방사선분포 및 계산상의 정확성 평가를 위하여 방사선치료 장비는 본 병원이 보유한 Clinac 2100CD (Varian, USA)를 이용하였고 폴리스티렌 팬텀과 필름 및 이온 전리함을 이용하여 방사선분포 및 계산상의 정확성을 평가하였다. 방사선분포의 평가 방법은 필름을 이용한 방사선분포의 중심부단면 선량분포와 CorePlan 에서 재현된 방사선분포의 동일면 선량분포를 비교하였다. 임상적용은 2003 년 3 월부터 7 월까지 방사선치료를 받은 50 명의 환자를 대상으로 분석하였다. 본 시험에 적용된 환자는 본 병원이 보유한 3 차원 방사선치료계획 장비인 Prowess 3D (SSGI Inc., USA)를 이용하여 실제 치료된 환자들이며 이 환자를 대상으로 CorePlan에서 동일하게 재현하여 비교하였다. 결과 및 결론 : 방사선분포 및 계산상의 정확성 평가에서는 실제 측정된 결과와 CorePlan에서 재현된 결과가 모두 $\pm$3% 이내로 평가되었다. 50 명의 환자를 대상으로 시행한 임상시험 결과 Prowess 3D에서 나타낸 결과와 비교하여 두경부에서는 1.678%, 흉부 1.578%, 복부 1.271%의 선량값의 오차를 보였다. 본 연구를 진행하는 과정에서 많은 부분의 프로그램 수정이 있었으며 실제임상에 필요한 부분에 대한 추가 및 보완이 이루어졌다. 앞으로 진행될 과정은 실제임상의 사용에 필요한 부분의 계속적인 업그레이드와 전자선에 대한 방사선분포 및 계산정확성 평가, 임상적용에 있어서 Prowess3D 뿐만 아니라 다양한 방사선 치료계획 장비와의 비교를 할 예정이다.

• Journal of Radiation Protection and Research
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• v.16 no.1
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• pp.25-32
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• 1991

MCNP code was used to calculate conversion factor H(d)ma at the depths of 0.07 and 10mm within a water phantom recommended by IAEA and within a PMMA phantom required by the US dosimeter proficiency testing programmes. The calculations were performed for an expanded parrallel beam of monoenergetic photons of perpendicular incidence on one faces of the phantom. The results can be used as conversion factor in calibrating individual dosemeters in terms of the dose equivalent quantities defined directly in the phantom.

• Progress in Medical Physics
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• v.16 no.3
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• pp.130-137
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• 2005

In total body irradiation (T81) for leukemia, we have a two methode. One is a AP (anterior-posterior) method and the other is a Lateral methode. Our hospital used lateral methode. T81 must consider about body contour, because of homogeneous dose distribution. For compensation about irregular body contour, we use compensator. For T81 treatment, we must be considered, accurate manufacture of compensator and accurate calculation of dose. We developed the automatic program for T81. This program accomplished for compensator design and dose calculation for irregular body. This program was developed for uses to use in a windows environment using the IDL language. In this program, it use energy data for each energy: TMR, output factor, inverse square law, spoiler, field size factor. This program reduces the error to happen due to the manual. As a development of program, we could decrease the time of treatment plan and care the patient accurately.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.18 no.3
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• pp.657-665
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• 2017

The aim of this study was to develop and distribute a dedicated program that can easily calculate the effective dose of a patient undergoing nuclear medicine examinations, and assist in the study of dose of nuclear medicine examinations and information disclosure. The program produced a database of the effective dose per unit activity administered (mSv/MBq) of the radiopharmaceuticals listed in ICRP 80, 106 Report and the fourth addendum, was designed through Microsoft Visual Basic (In Excel) to take the effect of 5 different (Area, Clark, Solomon(=Fried), Webster, Young) of pediatric dose calculation methods and 7 different body surface area calculation methods. The program calculates the effective dose (mSv) when the age, radionuclide, substance, and amount injected in the human body is inputted. In pediatric cases, when the age is entered, the pediatric method is activated and the pediatric method to be applied can be selected. When the BSA (Body Surface Area) formula is selected in the pediatric calculation method, a selection window for selecting the body surface area calculation method is activated. When the adult dose is input, the infant dose and the effective dose (mSv) are calculated automatically. The patient effective dose calculation program of the nuclear medicine examinations produced in this study is meaningful as a tool for calculating the internal exposure dose of the human body that is most likely to be obtained in nuclear medicine examinations, even though it is not the actual measurement dose. In the future, to increase the utilization of the program, it will be produced as an application that can be used in mobile devices, so that the public can access it easily.

• Journal of radiological science and technology
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• v.32 no.1
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• pp.39-43
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• 2009

The medical diagnostic examination using ionizing radiation has improved the patients' life and brought revolution in medical examination along with the mechanical development. However, the development of medical imaging systems has also been the reason to increase the patients' exposure for ionizing radiation. ICRP recommends that each country adopts diagnostic reference levels depending on regional and national situations. The Korea Food & Drug Administration suggested the dosimetry measurement guideline for patients in 2007. Nonetheless, in reality, it is hard to know the skin dose of the patients when applying a x-ray since there is no radiation dosimeter in most of clinical situation. Therefore, this study sets a program based on the bit system to figure out easily the skin dose of a patients using MS Excel program in the PC setting. The results showed 10% better outcome.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.10a
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• pp.333-333
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• 1998

• Journal of the Korean Society of Radiology
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• v.14 no.2
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• pp.169-178
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• 2020

The number of CT scans is increasing every year due to the improvement of the medical standards of the public, and thus the annual dose of medical radiation is also increasing. In this study, we evaluated the effective dose of the human body exposed to CT scans and estimated LAR. First, five region were selected from the CT diagnostic reference level guideline, and the effective dose of human body exposed to each examination was evaluated by clinical CT device. Second, the human organs and effective dose were calculated using the ALARA-CT program under the same conditions. Third, lifetime attributable risk (LAR) estimated by the effective dose exposed through the previous CT scan was estimated. As a result, the most effective dose was 21.18 mSv during the abdomen 4 phase scan, and the dose level was below DRL for all other tests except for the abdominal examination. As a result of evaluating effective dose using a dose calculation program under the same conditions, the results showed about 1.1 to 1.9 times higher results for each examination. In the case of organ dose, the closer the organ to the scan site, the higher the scattering ray. The lifetime attributable risk to CT radiation dose in adults was gradually decreased with age, and the results were somewhat different according to gender.

• Radiation Oncology Journal
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• v.7 no.2
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• pp.305-311
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• 1989

Fletcher-Suit colpostat has an internal structure to reduce dose to bladder and rectum. Some programs were developed to calculate dose at any point in water in three dimension around the colpostat containing Cs-137 tube, to find the shielding effect to dose by the internal structure, and to draw isodose curves and iso-shielding effect curves. Computer was an IBM compatible AT with EGA card and language was MS-Basic V6.0, Material, shape and geometry of the strucure, tube and colpostat were considered in algorithm for calculation of dose. Dose rates per unit mg. Ra. eq. in water calculated by a program were stored in auxiliary memory devices and retrieved in another programs. Isodose curves on medial side shrinked. Dose distribution was not symmetric about a transverse axis bisecting the colpostat. Reduction of dose was more excessive on top side than on bottom. Iso-shielding effect curve showed that the shielding effect was higher on top side than on bottom, and that there was shielding effect over almost all area of medial side. Such results were related to both shifted position of tube in the colpostat and asymmetric distribution of active source in the tube. Maximum of shielding effect was $49\%$ on top side and $44\%$ on bottom side. The direction of iso-shielding effect curve was generally radial from the center of active source. In treatment planning using Fletcher-Suit colpostat, the internal structure should be considered to find precise doses to bladder and rectum, etc.