• 한국정보통신학회논문지
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• 제23권7호
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• pp.779-785
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• 2019

인체공학적으로 개발된 Bismuth 차폐체를 뇌동맥류 코일 색전술에 적용함으로써 의료방사선 피폭으로부터 두피 및 수정체의 방사선 피폭을 감소시키고자 하였다. 광자극 형광 선량계를 이용하여 후두부, 양쪽 측두부, 양쪽 수정체부, 코 끝부를 개발된 Bismuth 차폐체를 사용 전 (A그룹) 후 (B그룹)로 측정하여 입사 표면 선량을 분석하였다. Bismuth 차폐체를 사용할 경우 화질에 대한 평가를 Signal to noise ratio (SNR)과 Contrast to noise ratio (CNR) 분석을 했다. A 그룹과 B 그룹의 입사 표면 평균 선량을 비교한 결과 A 그룹에 비해 B 그룹에서 평균 26.92% 감소되었다. CNR과 SNR의 분석은 로드맵과 디지털 감산조영 모두 동일하게 측정되었다. Bismuth 차폐체의 사용은 뇌혈관 중재적 시술 후 나타날 수 있는 일시적 탈모 및 기타 확률적 영향에 따른 방사선 장애를 화질의 저하 없이 감소시킬 수 있는 대안이 될 것으로 사료된다.

• Nuclear Engineering and Technology
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• 제52권8호
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• pp.1784-1791
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• 2020

The 14 MeV neutron generator facility is being developed by the Institute for Plasma Research India to conduct the lab scale experiments related to Indian breeding blanket system for ITER and DEMO. It will also be utilized for material testing, shielding experiments and development of fusion diagnostics. Occupational radiation exposure control is necessary for the all kind of nuclear facilities to get the operational licensing from governing authorities and nuclear regulatory bodies. In the same way, the radiation exposure for the 14 MeV neutron generator facility at the occupational worker area and accessible zones for general workers should be under the permissible limit of AERB India. The generator is designed for the yield of 10¹² n/s. The shielding assessment has been made to estimate the radiation dose during the operational time of the neutron generator. The facility has many utilities and constraints like ventilation ducts, accessible doors, accessibility of neutron generator components and to conduct the experiments which make the shielding assessment challenging to provide proper safety for occupational workers and the general public. The neutron and gamma dose rates have been estimated using the MCNP radiation transport code and ENDF -VII nuclear data libraries. The ICRP-74 fluence to dose conversion coefficients has been used for the assessment. The annual radiation exposure has been assessed by considering 500 h per year operational time. The provision of local shield near to neutron generator has been also evaluated to reduce the annual radiation doses. The comprehensive results of radiation shielding capability of neutron generator building and local shield design have been presented in the paper along with detailed maps of radiation field.

• 한국초전도ㆍ저온공학회논문지
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• 제4권2호
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• pp.73-77
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• 2002

In order to derive the detailed design of Thermal Shield Cryopanel. which plays a role to make the Tokamak Nuclear Fusion Equipment work at both static and efficient conditions the commercially available software package FLUENT Version 5.3, was utilized. This study investigated the effects of thermal sources and distributions on the temperatures of Lid. Body. Base. and EH-Port Cryopanel by the numerical technique whose grid generations cover the solid and 9as region of the panel. The physical model of the Thermal Shield Cryopanel is that the 10mm diameter of the pipe with 1mm thickness is soldered on the Stainless steel Panel with 4mm thickness. The heat fluxes to the panel are assumed to be by thermal radiation in the vacuum space and by conduction through the supporters. The inlet conditions of Helium gas are 20 atmospheric Pressures and 60K temperature. The panel shapes with cooling Pipes and the operational conditions to keep appropriate temperature distribution of Thermal Shield Cryopanel Have been found and suggested.

• 대한방사선기술학회지:방사선기술과학
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• 제44권3호
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• pp.189-194
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• 2021

This study was conducted to reduce the exposure dose to the breast and adjacent organs as the number of Mammography increased. Therefore, it has been designed a shield in lead, bismuth + tungsten, and bismuth that does not require to be equipped by the patient, in which each type of shield was compared and analyzed of radiation exposure dose to breast, thyroid, and eye. Using a mammography machine, optically stimulated luminescent dosimeter(OSLD) was inserted to bilateral breast, thyroid, and eye of a dosimetry phantom to measure dose radiated onto the phantom. Shielding device was made in different thickness of 2mm, 3mm, and 5mm and dose evaluation was performed by measuring the dose while using lead, bismuth, and bismuth + tungsten prosthesis. When each shields combined with shielding device, were compared of dose, all showed similar does reduction in the dose to breast, thyroid, and eye in both cranialcaudal and mediolateraloblique view. Based on the current study, bismuth and bismuth + tungsten can replace conventional lead shield and it is anticipated to safely and conveniently reduce radiation exposure to breast, thyroid, and eye with the shield that does not require to be equipped.

• 대한방사선기술학회지:방사선기술과학
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• 제43권3호
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• pp.169-176
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• 2020

Interventional radiology is performed under real-time fluoroscopy, and patients are exposed to a wide range of exposures for a long period of time depending on the examination and procedure. However, studies on radiation protection for patients during an intervention are insufficient. This study aims to evaluate the doses exposed during the intervention and the applicability of 3D printing materials. The organ dose for each intervention site was evaluated using a monte carlo simulatio. Also, the dose reduction effect of the critical organs was calculated when using a shielding device using 3D printing materials. As a result, the organ dose distribution for each intervention site showed a lower dose distribution for organs located far from the x-ray tube. It was analyzed that the influence of scattered rays was higher in the superficial organs of the back of the human body where x-rays were incident. The dose reduction effect on the critical organ using the 3D printing shield showed the highest testis among the gonads, and in the case of other organs, the dose reduction effect gradually decreased in the order of the eye, thyroid, breast, and ovary. Accordingly, it is judged that the 3D printed shield will be sufficiently usable as a shielding device for the radiation protection of critical organs.

• 한국전기전자재료학회논문지
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• 제22권6호
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• pp.476-483
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• 2009

Cosmic ray is composed of nuclear particles moving at a light speed. The cosmic ray affects the performance and the reliability of semiconductor devices by ionizing the semiconductor material. In this study, the radiation effects of protons, electrons, and photons, which compose the cosmic ray, on the GOS(Geostationary Orbit Satellite) were evaluated using the Monte-Carlo N-Particle code. The GOS was chosen due to the comparatively long exposure to the cosmic ray as it stays in the geostationary orbit more than 10 years. As the absorbed dose of semiconductor from electrons is much larger than those of protons, photons, and the secondary radiation, most of the radiation exposure of the semiconductors in the GOS results from that of electrons. When we compare the calculated absorbed dose with the radio-resistance of semiconductor, the Intel 486 of the Intel company is not suitable for the GOS applications due to its low radio-resistance. However RH3000-20 of MIPS and Motorola 602/603e can be applied to the Satellite when the aluminium shield is thicker than 3 mm.

• Nuclear Engineering and Technology
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• 제52권1호
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• pp.178-184
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• 2020

The traditional methods for radiation shield design always only focus on either the structure or the components of the shields rather than both of them at the same time, which largely affects the shielding performance of the facilities, so in this paper, a novel method for designing the structure and components of shields simultaneously is put forward to enhance the shielding ability. The method is developed by using the genetic algorithm (GA) and the MCNP software. In the research, six types of shielding materials with different combinations of elements such as polyethylene (PE), lead (Pb) and Boron compounds are applied to the radiation shield design, and the performance of each material is analyzed and compared. Then two typical materials are selected based on the experiment result of the six samples, which are later verified by the Compact Accelerator Neutron Source (CANS) facility. By using this method, the optimal result can be reached rapidly, and since the design progress is semi-automatic for most procedures are completed by computer, the method saves time and improves accuracy.

• 한국정보통신학회:학술대회논문집
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• 한국정보통신학회 2017년도 춘계학술대회
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• pp.179-182
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• 2017

뇌신경계 인터벤션시술은 장시간의 시술로 인해 피부의 수포 탈모 홍반등의 방사선 피폭으로 인한 위해가 빈번히 보고되어 지고 있다. 이에 CT(computed tomography) scan 시 피부 및 방사선 감수성이 예민한 인체의 전방부에 위치한 표적장기의 방사선 피폭을 감소시킬 목적으로 제작된 bismuth 차폐체를 인체공학적인 설계에 의하여 뇌혈관계 인터벤션 시술에 적용함으로써 방사선 감수성이 비교적 예민한 두피의 방사선 피폭 저감화를 위하여 연구를 제안 하고자 한다.

• 한국산학기술학회논문지
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• 제17권7호
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• pp.54-62
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• 2016

열을 전기로 바꾸는 장치로 가장 효율이 우수한 장치인 AMTEC은 알칼리금속을 작동유체로 하여 열을 직접적으로 전기로 변환시키는 장치이다. AMTEC은 저압용기, 고압용기, 베타 알루미나 고체 전해질, 그리고 순환윅으로 이루어져있다. AMTEC에서의 열손실은 주요하게 저압용기에서의 BASE와 응축부 사이에서 발생하는 열복사손실이며, 암텍의 발전량은 BASE의 온도유지력에 영향을 받기에 BASE의 표면온도를 고온으로 유지시켜주어야 고효율 발전량은 일정하게 유지할 수 있다. 이를 위하여 저압챔버에서의 복사 열손실을 줄이고 BASE온도는 상승시키고, AMTEC 시스템의 발전량 향상을 위하여 저압용기 내부의 6가지 형태의 열복사차단막에 따른 출력을 전산유체해석을 통하여 분석하였다. 분석에서 최적의 열복사차단막 형상은 수직부에 곡률을 가질 때이며, 그 때의 온도에 대한 무차원수(응축부온도/BASE온도 비)는 0.665 정도이고 출력은 약 17.69 W 정도로 다른 형상에 대비하여 높은 발전량을 갖는 것으로 계산되었다. 높이에 따른 발전량의 차이에서는 수평차단막이 BASE 상부로부터 멀리 떨어진 경우 발전량이 가장 우수하며, 17.58W 정도로 나타났다. 여러 개의 작은 홀과 다중 수평차단막을 설계한 경우는 기준이 되는 형상보다 오히려 발전량이 감소하였으며, 각각 0.91W, 2.06W 정도 감소하였다.

• Nuclear Engineering and Technology
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• 제53권4호
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• pp.1318-1322
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• 2021

To unveil and delineate the elements applicable to the radiation protection of a femoral entry shield, calculate its mass attenuation coefficient, and demonstrate its dose reduction efficacy for interventional radiologist performing transarterial embolization (TAE) of ruptured hepatocellular carcinoma (rHCC). The lead equivalency of the shield was firstly validated. Electron microscopy was used to confirm the femoral entry shield being lead-free and to analyze the elemental content, with which the mass attenuation coefficient of the shield was calculated. An adult phantom, irradiated at the upper abdomen to simulate the TAE of rHCC, was used together with a dosimeter attached to the palm of a hand phantom. The dose rates at the hand phantom were measured, with the rHCC clinical protocol, without and with the femoral entry shield placed over the right femoral access site of the adult phantom. Without using the shield, the average hand dose rate was measured to be 0.325 µSv/sec. While using the shield, it was determined to be 0.110 µSv/sec. There was significant 66% dose reduction to the hand dose of IRs performing angiographic intervention with the femoral entry shield.