• Proceedings of the KIEE Conference
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• 2006.04b
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• pp.369-371
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• 2006

반도체에 이온화 방사선을 조사시키면 소자 내부에서 전자-전공쌍(Electron-Hole Pair, EHP) 생성현상이 나타난나. 이 발성 전하는 방사선원에 따라 반영구적인 전원으로 활용이 가능하다. 본 논문에서는 반감기가 100여년인 Ni-63 베타 방사성 능위원소와 PN 접합형 반도체 소자를 사용한 방사선 전지를 개발하기 위한 연구의 일환으로 효율적인 방사광 변환 법과 전류 발생방법 및 전지회로 구현에 대해서 고찰하였다. 또한 Ni-63 방사선의 베타선 스펙트럼을 계산하고 이에 해당하는 광입력 특성에 대한 실리콘 PN 접합 다이오드의 반응특성을 태양광 시뮬레이션용 소프트웨어를 사용하여 검증하였다.

• The Journal of Korean Institute of Electromagnetic Engineering and Science
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• v.12 no.6
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• pp.1018-1024
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• 2001

In this paper, an array antenna is designed far base station of a street micro-cell in urban areas. It has a rectangular radiation pattern. The current distribution of the array is decided by using a modified Woodward-Lawson sampling pattern synthesis method. To confirm the realization of the array antenna with rectangular pattern, 12 array antenna with a planar type monopole fed by stripline is fabricated and measured. In the results of the measured values, H-plane pattern of the antenna nearly yields a rectangular radiation pattern.

• Proceedings of the Korea Water Resources Association Conference
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• 2004.05b
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• pp.1001-1006
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• 2004

본 연구에서는 요소를 사용하지 않고 절점들만을 이용하여 해석이 가능한 수치기법인 무요소절점법(element-free Galerkin method)의 개념을 선형파의 회절 및 방사문제에 적용하는 방법에 대해 연구하였다. 파동장에 놓인 부유식 구조물에 의한 연직 2차원 경계치 문제를 해석 대상으로 하였고, 파랑과 구조물의 상호작용을 해석함에 있어 구조물에 작용하는 동유체력과 이로 인한 구조물의 동적응답을 계산하기 위해서 무요소절점법을 이용하였다. 무요소절점법의 수식화과정을 체계적으로 정리하였으며, 무요소절점법의 타당성 및 적용성을 입증하기 위해서 직사자형 부유체에 내한 수치해석을 실시하여 타 논문의 결과와 비교하였다. 또한 해의 정확도에 직접적으로 영향을 미치는 절점간격과 파수와의 관계에 대한 기준 설정을 위한 수치실험도 수행하였다.

• 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 Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.16 no.3
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• pp.377-387
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• 2018

Korea's first commercial nuclear power plant, Kori Unit 1, was permanently shut down on June 18, 2017, after 40 years of successful operation. Kori Unit 1 plans to construct a waste treatment facility in the turbine building prior to commencement of dismantling in earnest. Various radioactive wastes are decontaminated, disassembled, cut and melted in the waste treatment facility and sent to the radioactive waste repository. The proportion of metal radioactive waste in dismantled waste is about 70%, of which large metal radioactive waste is mainly generated in the primary circuit and has high radioactivity, so radiation exposure must be managed during disassembly. In this study, the steam generators are selected as large metal radioactive waste, the exposure doses of the dismantling workers are calculated using RESRAD-RECYCLE code and the methods for reducing the exposure doses are suggested.

• The Journal of Korean Institute of Electromagnetic Engineering and Science
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• v.12 no.6
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• pp.983-993
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• 2001

This paper proposed a novel chip type ceramic dielectric antenna by using the advanced meander line technique that the radiational metals are formed on the face of ceramic dielectric(8$\times$4$\times$1.5 mm, alumina) and both faces of substrate(1.0 mm thickness, FR-4). The performance of the antenna model has a good agreements between measurements and computed results. Resultly, it has a 10 dB return-loss bandwidth(2.4∼2.4835 GHz) and 1.7 dBi measured radiation gain for Bluetooth application. The proposed antenna model can overcome the limited radiation of the small-sized antenna.

• Journal of the Korean Society of Radiology
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• v.9 no.5
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• pp.295-300
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• 2015

There are various type of particle accelerators such as Kyoungju 100-MeV proton beam accelerator in Korea. And Korea plans to build large particle accelerator such as heavy ion accelerator and 4th generation light source facility. The accelerated high energy particles of these facility produce 2nd neutron after nuclear reaction with target materials. And then these 2nd neutron activate structural materials and surrounding environment. Accordingly, it is important to consider the activation and shielding calculation on design of facility for safety operation. In this study, we tried to calculate and compare the neutron flux from the interaction $^{la}150$ beam with target material(Cu) according to thickness of iron and concrete shielding material by MCNPX 2.7 with nuclear library JENDL/HE 07and la150. To verify the properties of nuclear library, we compared computational results with experimental value. These results can be used for dose evaluation technology in planning of the shielding of large particle accelerator.

• Journal of the Korean Society of Radiology
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• v.13 no.7
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• pp.917-924
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• 2019

The passive scattering system nozzle of the proton therapy accelerator was simulated to evaluate the neutrons generated by each component in each nozzle by energy. The Monte Carlo N-Particle code was used to implement spread out Bragg peak with proton energy 220 MeV, reach 20 cm, and 6 cm length used in the treatment environment. Among the proton accelerator components, neutrons were the highest in scatterers, and the neutron flux decreased as it moved away from the central flux of the proton. This study can be used as a basic data for the evaluation of the radiation necessary for the maintenance and dismantling of proton accelerators.

• Journal of the Korean Society of Radiology
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• v.8 no.3
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• pp.97-103
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• 2014

Decommission of medical cyclotron give rise to a lot of low-level radioactive waste and costs. Decommissioning cost should be reasonably calculated according to the decommissioning activities and installed components of facilities. In this paper, we investigated the experience on the cyclotron relocation from SNUH(Seoul National University Hospital) to SKKU(Sungkyunkwan University) and analyzed radioactive waste management costs by applying the disposal scenarios. Also considerations for decommissioning cost estimation are reviewed. The results could be utilized as a basic data for establishment on the methodology of decommissioning cost estimation and evaluation.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.381-387
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• 2003

Hull arising from the spent PWR fuel elements is classified as a high-level radioactive waste. This report describes the radio-chemical characteristics of the hull -from PWR spent fuel of 32, 000MWd/tU burn-up and 15 years cooling, discharged from Gori Unit I cycled 4 -7-by examination and literature survey. On the basis of the results, a method of degradation to middle and low-level radio active waste was proposed by dry process such as laser or plasma technique with removing the nuclides deposited on the surface of the hull.