• Journal of Radiation Protection and Research
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• 제3권1호
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• pp.37-43
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• 1978

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1999년도 추계학술발표회요약집
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• pp.326.2-326
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• 1999

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1999년도 추계학술발표회요약집
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• pp.312.2-312
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• 1999

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2019년도 춘계학술논문요약집
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• pp.241-242
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• 2019

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2002년도 Proceedings
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• pp.138-140
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• 2002

The spinal cord dose is the one of the limiting factor for the radiation treatment of the head & neck (H&N) or the thorax region. Due to the fact that the cord is the elongated shaped structure, it is not an easy task to maintain the cord dose within the clinically acceptable dose range. To overcome this problem, the spinal cord partial block technique (PBT) with the dynamic Multi-Leaf Collimator (dMLC) has been developed. Three dimension (3D) conformal beam directions, which minimize the coverage of the normal organs such as the lung and the parotid gland, were chosen. The PBT field shape for each field was designed to shield the spinal cord with the dMLC. The transmission factors were determined by the forward calculation method. The plan comparisons between the conventional 3D conformal therapy plan and the PTB plan were performed to evaluate the validity of this technique. The conformity index (CI) and the dose volume histogram (DVH) were used as the plan comparison indices. A series of quality assurance (QA) was performed to guarantee the reliable treatment. The QA consisted of the film dosimetry for the verification of the dose distribution and the point measurements. The PBT plan always generated better results than the conventional 3D conformal plan. The PBT was proved to be useful for the H&N and thorax region.

• 한국의학물리학회지:의학물리
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• 제29권2호
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• pp.66-72
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• 2018

The proper position of a multi-leaf collimator (MLC) is essential for the quality of intensity-modulated radiation therapy (IMRT) and volumetric modulated arc radiotherapy (VMAT) dose delivery. Task Group (TG) 142 provides a quality assurance (QA) procedure for MLC position. Our study investigated the QA validation of the mechanical leaf gap measurement and the maintenance procedure. Two $VitalBeam^{TM}$ systems were evaluated to validate the acceptance of an MLC position. The dosimetric leaf gaps (DLGs) were measured for 6 MV, 6 MVFFF, 10 MV, and 15 MV photon beams. A solid water phantom was irradiated using $10{\times}10cm^2$ field size at source-to-surface distance (SSD) of 90 cm and depth of 10 cm. The portal dose image prediction (PDIP) calculation was implemented on a treatment planning system (TPS) called $Eclipse^{TM}$. A total of 20 VMAT plans were used to confirm the accuracy of dose distribution measured by an electronic portal imaging device (EPID) and those predicted by VMAT plans. The measured leaf gaps were 0.30 mm and 0.35 mm for VitalBeam 1 and 2, respectively. The DLG values decreased by an average of 6.9% and 5.9% after mechanical MLC adjustment. Although the passing rates increased slightly, by 1.5% (relative) and 1.2% (absolute) in arc 1, the average passing rates were still within the good dose delivery level (>95%). Our study shows the existence of a mechanical leaf gap error caused by a degenerated MLC motor. This can be recovered by reinitialization of MLC position on the machine control panel. Consequently, the QA procedure should be performed regularly to protect the MLC system.

• Journal of Radiation Protection and Research
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• 제34권3호
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• pp.129-136
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• 2009

국내 원전의 계획예방정비기간 중에 원자로계통의 개방과정에서 원자로건물내 공기 중으로 누설된 $^{131}I$의 체내 흡입으로 원전종사자의 내부피폭이 발생하였다. 이에 따라 원전에서 보유하고 있는 전신계측기(Whole body counter)를 이용하여 내부방사능을 측정하였다. 이들 측정값을 근거로 국제방사선방호위원회(ICRP)의 내부피폭 선량평가 지침을 적용하여 섭취량을 산정하고, 내부 피폭 방사선량을 평가하였다. $^{131}I$은 체내에서 섭취와 배설이 빠르고 갑상선으로 재축적이 일어나기 때문에 섭취 후 측정시점에 따라 섭취량이 차이를 보였다. 또한 ICRP 간행물에서 $^{131}I$의 전선에 대한 섭취잔류분율 자료를 제공하고 있지 않아 갑상선 섭취잔류분율 자료를 이용함으로써 섭취량 평가에서 오차를 나타내었다. 이에 따라 수계산과정으로 섭취량을 산정하고 예탁유효선량을 평가하였다. 한편 전선에 대한 섭취잔류분율을 새로 계산하였으며, 이 결과를 검증하였다. 또한 국제적으로 이용되고 있는 내부 피폭 선량평가 전신코드들 이용하여 섭취량 산정과 내부피폭 선량평가 평가결과에 대한 비교 계산이 병행하여 이루어졌다.

• Journal of Radiation Protection and Research
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• 제45권4호
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• pp.178-186
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• 2020

Background: Reactor pressure vessel (RV) with internals (RVI) are activated structures by neutron irradiation and volume contaminated wastes. Thus, to develop safe and optimized disposal plan for them at a disposal site, it is important to perform exact activation calculation and evaluate the dose rate on the surface of casks which contain cut-off pieces. Materials and Methods: RV and RVI are subjected to neutron activation calculation via Monte Carlo methodology with MCNP6 and ORIGEN-S program-neutron flux, isotopic specific activity, and gamma spectrum calculation on each component of RV and RVI, and dose rate evaluation with MCNP6. Results and Discussion: Through neutron activation analysis, dose rate is evaluated for the casks containing cut-off pieces produced from decommissioned RV and RVI. For RV cut-off ones, the highest value of dose rate on the surface of cask is 6.97 × 10-1 mSv/hr and 2 m from it is 3.03 × 10-2 mSv/hr. For RVI cut-off ones, on the surface of it is 0.166 × 10-1 mSv/hr and 2 m from it is 1.04 × 10-1 mSv/hr. Dose rates for various RV and RVI cut-off pieces distributed lower than the limit except the one of 2 m from the cask surface of RVI. It needs to adjust contents in cask which carries highly radioactive components in order to decrease thickness of cask. Conclusion: Two types of casks are considered in this paper: box type for very-low-level waste (VLLW) as well as low-level waste (LLW) and cylinder type for intermediate-level waste (ILW). The results will contribute to the development of optimal loading plans for RV and RVI cut-off pieces during the decommissioning of nuclear power plant that can be used to prepare radioactive waste disposal plans for the different types of wastes-ILW, LLW, and VLLW.

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2002년도 Proceedings
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• pp.248-251
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• 2002

The intensity modulated radiation therapy (IMRT) with a multileaf collimator (MLC) requires the conversion of a radiation fluence map into a leaf sequence file that controls the movement of the MLC during radiation treatment of patients. Patient dose verification is clinically one of the most important parts in the treatment delivery of the radiation therapy. The three dimensional (3D) reconstruction of dose distribution delivered to the target helps to verify patient dose and to determine the physical characteristics of beams used in IMRT. A new method is presented for the pretreatment dosimetric verification of two dimensional distributions of photon intensity by means of Beam Intensity Scanner System (BISS) as a radiation detector with a custom-made software for dose calculation of fluorescence signals from scintillator. The scintillator is used to produce fluorescence from the irradiation of 6MV photons on a Varian Clinac 21EX. The BISS reproduces 3D- relative dose distribution from the digitized fluoroscopic signals obtained by digital video camera-based scintillator(DVCS) device in the IMRT. For the intensity modulated beams (IMBs), the calculations of absorbed dose are performed in absolute beam fluence profiles which are used for calculation of the patient dose distribution. The 3D-dose profiles of the IMBs with the BISS were demonstrated by relative measurements of photon beams and shown good agreement with radiographic film. The mechanical and dosimetric properties of the collimating of dynamic and/or step MLC system alter the generated intensity. This is mostly due to leaf transmission, leaf penumbra and geometry of leaves. The variations of output according to the multileaf opening during the irradiation need to be accounted for as well. These phenomena result in a fluence distribution that can be substantially different from the initial and calculative intensity modulation and therefore, should be taken into account by the treatment planning for accurate dose calculations delivered to the target volume in IMRT.

• 한국의학물리학회지:의학물리
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• 제24권1호
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• pp.48-53
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• 2013

몬테카를로 방식은 지금까지 인체 내 흡수선량을 계산하는 가장 정확한 방법으로 알려져 왔고. 이러한 계산 방법을 이용하기 위한 인체 내부의 장기 묘사는 인체 모형 팬텀이 주로 사용되어 왔다. 그러나 최근 Geant4 코드를 사용한 몬테카를로 계산에서는 CT의 DICOM 파일에서 인체의 여러 장기에 대한 자료를 직접 추출하고 시뮬레이션에 필요한 geometry로 변환하여 사용하려는 다양한 노력이 시도되고 있다. 이와 같은 기능은 실제 인체의 해부학적 구조를 그대로 재현하면서 인체 내부의 흡수선량을 정확히 계산 할 수 있도록 한다. 따라서 본 연구에서는 DICOM 파일을 연동한 Geant4을 이용하여 인체 내 흡수선량을 계산하였고, 이를 Gafchromic EBT2 필름을 이용한 측정 선량과 비교함으로써 그 유용성을 확인하고자 하였다. 본 연구에서 시뮬레이션을 이용하여 계산한 선량과 EBT2 필름을 이용한 선속 중심축에서의 측정선량을 비교한 결과 피부표면에서부터 최대선량 깊이까지 선량이 급격하게 변화하는 build up 영역을 제외하고는 오차(difference) 범위가 평균 3.75% 임을 알 수 있었다. 또한 선량의 계산 값을 각 CT slice 별로 출력되도록 하였고, 또 각 slice에서도 복셀 하나하나의 선량 값이 출력되도록 하여 측정하고자 하는 장기별, 기관별 흡수선량을 쉽게 확인 할 수 있도록 하였다. 이처럼 인체 모형 팬텀이 아닌 실제 인체의 image data인 CT DICOM 파일을 이용한 선량계산을 각 slice, voxel 별로 선량 값을 출력하는 방식은 다양한 부위의 정확한 선량계산을 가능하게 하므로 향후 방사선 치료계획 시스템의 선량 계산에 유용할 것이라 생각한다. 또한 현재 사용 중인 여러 에너지 영역에도 적용이 가능하므로 인체 내 방사선의 흡수선량 확인을 위해 유용하게 활용되어질 수 있을 것으로 생각된다.