• The Journal of Korean Society for Radiation Therapy
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• v.26 no.2
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• pp.321-327
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• 2014

Purpose : To verify the accuracy of the Ecilpse's dose calculation algorithm(AAA:Analytic anisotropic algorithm) in case of a radiation treatment on Inhomogeneous tissues using FFF beam comparing dose distribution at TPS with actual distribution. Materials and Methods : After acquiring CT images for radiation treatment by the location of tumors and sizes using the solid water phantoms, cork and chest tumor phantom made of paraffin, we established the treatment plan for 6MV photon therapy using our radiation treatment planning system for chest SABR, Ecilpse's AAA(Analytic anisotropic algorithm). According to the completed plan, using our TrueBeam STx(Varian medical system, Palo Alto, CA), we irradiated radiation on the chest tumor phantom on which EBT2 films are inserted and evaluated the dose value of the treatment plan and that of the actual phantom on Inhomogeneous tissue. Results : The difference of the dose value between TPS and measurement at the medial target is 1.28~2.7%, and, at the side of target including inhomogeneous tissues, the difference is 2.02%~7.40% at Ant, 4.46%~14.84% at Post, 0.98%~7.12% at Rt, 1.36%~4.08% at Lt, 2.38%~4.98% at Sup, and 0.94%~3.54% at Inf. Conclusion : In this study, we discovered the possibility of dose calculation's errors caused by FFF beam's characteristics and the inhomogeneous tissues when we do SBRT for inhomogeneous tissues. SBRT which is most popular therapy method needs high accuracy because it irradiates high dose radiation in small fraction. So, it is supposed that ideal treatment is possible if we minimize the errors when planning for treatment through more study about organ's characteristics like Inhomogeneous tissues and FFF beam's characteristics.

• Korean Journal of Digital Imaging in Medicine
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• v.7 no.1
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• pp.45-49
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• 2005

목적 : 기존 구내 방사선 촬영에서 사용되었던 Film에서의 노출선량과 Digital Sensor를 이용한 구내 디지털 촬영에서의 노출선량을 비교하여 현재 광범위 하게 사용 되어지고 있는 Digital Sensor가 환자의 피폭선량을 감소하는데 기여하는 정도를 알아본다. 대상 및 방법 : 치아 우식증이 없는 5개의 구치부 치아를 선택하여 석고 블럭에 매식한 후 교합면과 인접면에 우식병소들을 형성하였다. 이를 필름(Kodak Insight; IS, Kodak Co, USA)과 Digital Sensor(Kodak RVG 6000; Kodak Co, USA)에 XCP Instrument(Rinn Co, USA)를 사용하고, 전면에는 조직등가물질인 Acrylic Resin Block 20mm를 설치하였다. Acrylic Resin Block의 관구 측면 에서는 조사선량계를 부착하여 단계별로 변화시키는 노출조건에 대한 조사선량을 측정하였다. 그리고 이렇게 얻어진 영상을 3명의 방사선학 전공의와 1명 의 보존과 전공의가 평가를 하였다. 결과 : Film과 Digital Sensor를 가지고 촬영한 영상을 분석한 결과 노출선량에서도 Digital Sensor는 Film 노출선량과 비슷한 결과를 도출해 낼 수 있었다. 그러나 Digital Sensor로 촬영된 영상의 경우에는 Film 경우보다 좀더 효과적으로 조사선량을 판단 할 수 있었으며, 또한 영상 판독시 필름보다 폭 넓게 응용 할 수 있었다. 결론 : 본 연구에서는 선량 변화에만 의존하는 것이 아니라 Digital Sensor로 촬영시 영상 조절을 병행한다면 좀더 정확하고 효과적인 진단 활동에 도움이 될 수 있을 것으로 사료된다.

• Progress in Medical Physics
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• v.4 no.1
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• pp.17-21
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• 1993

근접방사선치료는 방사성동위원소를 종양에 밀착시키거나 또는 종양내에 직접 삽입하여 치료하는 방법으로서 종양에는 일시에 많은 선량을 주는 반면 주위 정상조직에는 선량을 최소화시킬 수 있는 장점이 있다. 따라서 근래에 들어 종양치료에 있어서 외부방사선치료와 병행하여 근접방사선치료를 시행하는 병원이 증가하고 있다. 그러나 근접방사선치료는 방출 방사선의 에너지가 낮고, 대부분 짧은 반감기를 가지며, 소형의, 수 mCi에서 수Ci 정도의 방사능을 가진 방사성동위원소들을 인체에 직접 삽입하는 것으로 정확한 선량 분포를 위해서는 방사성동위원소의 방사능량, 위치, 분포 등의 정확성 확보가 절실히 요구된다. 따라서 이 논문은 근접방사선치료시스템의 QA프로그램 개발을 위하여 작성하였다.

• Radioisotope journal
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• v.15 no.3
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• pp.78-92
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• 2000

낮은 선량의 방사선피폭으로 인한 건강 위해의 여부에 대하여 과학적 현황을 고찰하였다. 선량과 영향 사이에 문턱 없는 선형비례 모델(LN-T모델)에 대해 역학적, 수학적, 방사선생물학적 측면의 긍정적 논리와 호메시스, 적응반응, 통계적 관점의 비판적 논거를 대비하여 평가하였다. 방사선 피폭이력자에게 발현한 확률적 영향 특히 백혈병을 포함한 암에 대해 그 질환의 방사선 인과성 판단에 대한 애로와 접근 방향을 논의하였다. 객관적인 평가 지표의 하나로 기인확률(PC)을 적용하되 근로자에 대한 제도적 배려 등 고려할 사항을 논의하였다.

• The Journal of the Korea Contents Association
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• v.15 no.3
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• pp.192-198
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• 2015

Checked out by the moving vehicle health checks for patients, practitioners, and the increase in radiation dose outside the vehicle, but an investigation into the leakage of radiation can still be negligible. In this study, through experimental results were as follows: Dose that occurs most often where the leak in the right door $1.14{\pm}1.75mR/h$, X-ray generator in terms of proximity to the top $0.65{\pm}1.25mR/h$, X-ray generator and away to the bottom in terms $0.91{\pm}1.25mR/h$, the adjacent rear detector in the upper part $96.98{\pm}158.88mR/h$ dose of the leak appeared in various locations. By measuring position from the rear of the adjacent detector $67.48{\pm}97.03mR/h$ dose had the highest leakage into. Generating device for diagnosis of radiation safety regulations regarding the maximum leakage dose per week, but all met back when it is displayed in the leakage dose Hourly rates do not ignore the leakage radiation dose were measured. Therefore, a mobile health screening in a vehicle outside of the leakage radiation dose to the liver and move on we are not interested twelve barrier leakage radiation dose of defense has a chance to re-evaluate the standards required, and move the vehicle health check using the X-ray increases as the dose per hour, depending on the criteria for choosing the appropriate measures that will require effort.

• Journal of radiological science and technology
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• v.30 no.1
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• pp.33-38
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• 2007

The propose of this study is a verification of the correct calculation of the dose around source and the prescription dose of Ir-192 source in the plato treatment planning system. The source and orthogonal coordinates for lateral direction and those for the anterior posterior direction were drawn on a A4 paper and then input into the system. The prescription dose was prescribed to two points with radius 1 cm in the direction of polar angle $90^{\circ} and $270^{\circ} from the center of the source. The doses of prescription point and dose points acquired from the treatment planning system were compared with those from manual calculation using the geometry function formalism derived by Paul King et al. In this analysis, the doses of prescription point were exactly consistent with each other and those of dose points were obtained within the error point of 1.85%. And the system of accuracy was evaluated within 2% of tolerance error. Therefore, this manual dose calculation used for the geometry function formalism is considered to be useful in clinics due to its convenience and high quality assurance.

• Journal of Radiation Protection and Research
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• v.36 no.3
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• pp.168-173
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• 2011

This study investigated characteristics of dose distribution at junction field of X-ray and electron beams according to the method for fabricating the insert block on the electron cone. Insert block were fabricated to the divergency cutout block and the straight cutout block. For the 6 MV X-ray and 10 MeV nominal energy of electron beam, we was adjacent to the light field of X-ray and electron beam at a surface of matrix chamber and measured to beam profile of abutted field in the 0, 1, 2, 3 cm measurement depth. As a result, characteristics of dose distribution at junction field, straight block was existent that over dose area exceed the give dose more than 5% and under dose area with a rapid change in dose distribution. However, divergency block had remarkably decreased the over dose area caused by the lateral scattering effects of decrease, and being existed uniformity dose distribution in the junction field. Therefore, divergency block were the benefits of radiation dose delivery, in order to applied the clinical, measurement of electron beams according to the fabrication method of the block should be considered carefully.

• The Korean Journal of Nuclear Medicine Technology
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• v.18 no.2
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• pp.57-61
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• 2014

Purpose Iodine (I-131) is one of the most widely used radioactive isotopes for therapeutic in the field of nuclear medicine. Therapeutic I-131 capsule is made out of lead to shield high energy radiation. Accurate dosimetry is necessarily required to perform safe and effective work for relative workers. The Monte Carlo method is known as a method to predict the absorbed dose distribution most accurately in radiation therapy and many researchers constantly attempt to apply this method to the dose calculation of radiotherapy recently. This paper aims to calculate distance dependent and activity dependent therapeutic I-131 capsule using GEANT4. Materials and Methods Therapeutic capsules was implemented on the basis of the design drawings. The simulated dose was determined by generating of gamma rays of energy to more than 364 keV. The simulated dose from the capsule at the distance of 10 cm and 100 cm was measured and calculated in the model of water phantom. The simulated dose were separately calculated for each position of each detector. Results According to the domestic regulation on radiation safety, the dose at 10 cm and 100 cm away from the surface of therapeutic I-131 capsule should not exceed 2.0 mSv/h and 0.02 mSv/h, respectively. The simulated doses turned out to be less than the limit, satisfying the domestic regulation. Conclusion These simulation results may serve as useful data in the prediction of hands dose absorbed by I-131 capsule handling. GEANT4 is considered that it will be effectively used in order to check the radiation dose.

• Journal of Radiation Protection and Research
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• v.36 no.2
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• pp.99-106
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• 2011

Tritium is the one of the most important radionuclide for workers in nuclear power plants (NPPs) and the public, from the dosimetric point of view. Humans are likely to have internal radiation exposure by tritium inhalation. Radiation exposure by tritium accounts for approximately 7% and 60~90% of the total radiation exposure of NPP workers and the public during normal operation, respectively. Thus, many researches have been conducted to estimate the internal dose by tritium precisely in the world. In terms of tritium dosimetry, this paper provides the current status of research for tritium metabolism and dosimetry.

• The Journal of the Korea Contents Association
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• v.16 no.7
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• pp.451-456
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• 2016

To analyse the absorbed radiation dose of the visual organs (eyes, corneas, lenses) during a head CT scan, a with the purpose of radiation protection was designed. Afterwards, the reduction rate of radiation dose when using an eye-shielding was analyzed. The results showed that the higher the energy, the higher the absorbed dose of the eyes. Excluding the head, the organs with high dose were the eyes, corneas, and lenses, respectively. Furthermore, the dose reduction rate before and after shielding was between 38% and 55% for the eyes, and between 35% and 52% for the corneas. In the case of the lenses, when the front was shielded, the reduction rate was 51%, and when the front and the side were shielded simultaneously, the reduction rate was 67%.