• Journal of the Korea Convergence Society
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• v.12 no.10
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• pp.129-136
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• 2021

Radiation shields used in medical institutions mainly use lead to manufacture products and fitments. Although lead has excellent processability and economic efficiency, its use is being reduced due to environmental issues when it is disposed of. In addition, when used for a long time, there is a limit to using it as a shielding film, shielding wall, medical device parts, etc. due to cracking and sagging due to gravity. To solve this problem, copper, tin, etc. are used, but tungsten is mostly used because there is a difficulty in the manufacturing process to control the shielding performance. However, it is difficult to compare with other shielding materials because the characteristics according to the type of tungsten are not well presented. Therefore, in this study, a medical radiation shielding sheet was manufactured in the same process using pure tungsten, tungsten carbide, and tungsten oxide, and the particle composition and shielding performance of the sheet cross-section were compared.As a result of comparison, it was found that the shielding performance was excellent in the order of pure tungsten, tungsten carbide, and tungsten oxide.

• The Journal of the Institute of Internet, Broadcasting and Communication
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• v.19 no.2
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• pp.59-65
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• 2019

The EMI shielding effectiveness of shielding layers thickness was analyzed when the low conductivity shielding layers was placed in the near field of the noise source. A spiral antenna with broadband characteristics was used as the noise source, and graphite was selected as the low conductivity shielding material. Two spiral antennas were constructed to analyze the transmission coefficient between two antennas, and the distances between the transmitting and receiving antennas were 5 cm and 10 cm. The thickness of the shielding layers was changed from 1 um to 200 um. The frequency was changed from 100 MHz to 6 GHz to obtain a maximum SE(Shielding Effectiveness) of 70 dB. In this simulation, electronic shielding was used due to the nature of graphite, which is a shielding film material. Based on these results, we will study how to improve the shielding performance by implementing magnetic shielding in the future.

• Journal of the Korea Convergence Society
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• v.12 no.11
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• pp.119-126
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• 2021

Radiation shielding clothing for medical institutions is used based on lead equivalent of 0.25 mmPb. However, this study intends to study the shielding suit that can guarantee the user's activity while considering the sensitivity of each part of the body. By manufacturing based on eco-friendly shielding material, it was attempted to solve the weight problem and environmental problem of existing lead aprons, and to present the same shielding performance as lead equivalent in thickness. The fabric of the produced shielding sheet was manufactured through a calendar process that adjusts the thickness of the shielding sheet from lead equivalent 0.12 mmPb to 0.32 mmPb. In addition, the usability evaluation of the manufactured shielding clothes was conducted for the subjects who were workers in medical institutions. As a result, the activity became easier and the weight was reduced by 0.26 kg. In the future, it is thought that it is necessary to improve the shielding suit design considering the activity.

• Journal of the Korean Society of Radiology
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• v.18 no.1
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• pp.11-20
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• 2024

As the importance of intervention has recently increased, interest in the health of medical staff performing the procedure is increasing. Existing radiation shielding devices have limited the operator's movement and have not been properly used due to the risk of infection, and adequate radiation shielding of the operator's gonads and furthermore, the entire area of the procedure room has not been achieved. An auxiliary shielding device was manufactured by attaching a Bismuth to the elbow support used in the procedure, and the radiation shielding effect was measured. As a result of the measurement, the average spatial dose rate decreased by about 64.8%, and the independent sample t-test analysis showed statistically significant below the significance probability (p<0.05). The use of an auxiliary shielding device is considered to be an effective shielding method that can shield the operator's gonads and reduce the radiation spatial dose rate of the entire area of the procedure room.

• Proceedings of the Korea Contents Association Conference
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• 2015.05a
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• pp.175-176
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• 2015

몬테카를로 기법을 기반으로 한 모의실험을 통해 방사성 핵종별 주사기 차폐기구의 재질 및 두께에 대한 차폐분석 결과, 텅스텐, 납, 비스무스 경우 가장 높은 차폐효과를 보였다. 그러나 $^{18}F$ 선원의 경우, 차폐두께가 낮은 영역에서 저 원자번호 재질보다 더 높은 에너지를 나타냈으나, 이후 증가된 차폐두께에서는 더 낮은 에너지 분포를 나타냈다. 그 외 재질의 경우 구리, 철, 스테인리스 강, 황산바륨의 순서로 에너지가 낮은 분포를 나타냈고, 알루미늄, 플라스틱, 콘크리트, 물의 경우 핵종별로 각기 다른 양상을 나타냈으며, 상대적으로 감마선의 투과의 증가로 인해 전체적으로 차폐효과가 떨어지는 것으로 나타냈다.

• Journal of the Korean Ceramic Society
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• v.38 no.1
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• pp.15-21
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• 2001

전자파 차폐 및 반사방지용으로 사용되는 SiO$_2$/ITO 이층박막의 전기적 특성에 미치는 전이금속이온의 영향에 대해 고찰하고 전자파 차폐이론식으로부터 박막의 전도특성에 모사하여 효과적인 전자파 차폐효과를 얻기 위한 전도막을 설계하고자 하였다. ITO 상층부에 전이금속염을 첨가한 실리카 복합졸을 코팅하여 SiO$_2$/ITO 이층막을 제조한 결과 최저 표면저항치를 나타내는 첨가량은 전이금속의 종류에 따라 차이를 보이지만 Sn 및 Zn이 첨가된 졸로부터 형성된 박막은 $10^{5}$Ω/$\square$ 이하의 낮은 저항치를 보였으며 가장 안정된 표면저하을 나타내었다. 또한 전자파 차폐효과와 전도박막의 표면저항을 차폐이론식으로부터 모사한 결과 Zn과 Sn의 전이금속염이 첨가된 SiO$_2$/ITO 투명전도막은 TCO99에서 정한 전자파 차폐기준에 부합하였다.다.

• Proceedings of the Korea Water Resources Association Conference
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• 2007.05a
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• pp.1963-1966
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• 2007

본 연구에서는 기존의 IIR 필터가 아닌 장기간의 누적 반사도자료를 활용하여 실제 레이더 반사도의 감쇄정도를 정량적으로 파악하고 차폐지역 후면의 반사도를 보정하여 강우산정시 기초자료인 반사도 자료처리에서 개선된 품질관리기법을 적용하여 그 결과를 분석해보고자 하였다. 개발된 품질관리기법을 적용한 사례분석 결과, 기 IIR필터에 의한 지형에코제거에 비해 강수에코의 제거현상 등의 오차발생이 줄어들고 차폐보정으로 반사도 강도도 향상되었다. 실제 C밴드에 비해 감쇄의 영향이 적은 광덕산 S밴드 레이더와 비교한 결과에서도 차폐보정을 통하여 완전차폐를 제외한 부분차폐지역의 경우 상당히 개선된 결과를 보여주었다.

• Review of KIISC
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• v.33 no.6
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• pp.45-49
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• 2023

뉴스페이스 시대가 도래하고 양자컴퓨터로 기존 암호체계의 파훼가 수월해진 오늘날 인공위성의 보안모듈은 고성능의 상용 부품을 필요로 한다. 본 연구에서는 PE와 Al의 복합소재를 활용하여 내방사선 능력이 적은 상용 부품을 사용한 인공위성 탑재 보안모듈의 차폐 방안을 제시하였다. 기존의 Al 단일 소재로 제작된 차폐 하우징의 성능과 경제성을 개선하기 위해 PE와 Al의 복합소재를 연구하였다. 이를 위해 OMERE를 통해 저궤도 위성의 임무 환경을 분석하여 PE와 Al 복합소재의 우주방사선 차폐성능과 Al 단일 소재의 우주방사선 차폐성능을 PHITS와 SRIM을 이용하여 비교분석하였다. 연구 결과, PE와 Al의 복합소재를 활용한 차폐 하우징은 가볍고 경제적인 장점을 가지며, 성능도 크게 향상됨을 확인하였다. 이러한 연구 결과는 보안모듈에 한정되지 않고 위성 부품의 차폐에 새로운 가능성을 제시함으로써, 전반적인 우주산업 발전과 위성의 임무 수행 실패율 감소에 기여할 수 있다.

• Journal of Radiation Protection and Research
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• v.39 no.1
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• pp.21-29
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• 2014

A new cold neutron triple-axis spectrometer (Cold-TAS) was recently constructed at the 30 MWth research reactor, HANARO. The spectrometer, which is composed of neutron optical components and radiation shield, required a redesign of the segmented monochromator shield due to the lack of adequate support of its weight. To shed some weight, lowering the height of the segmented shield was suggested while adding more radiation shield to the top cover of the monochromator chamber. To investigate the radiological effect of such change, we performed MCNPX simulations of a few different configurations of the Cold-TAS monochromator shield and obtained neutron and photon intensities at 5 reference points just outside the shield. Reducing the 35% of the height of the segmented shield and locating lead 10 cm from the bottom of the top cover made of polyethylene was shown to perform just as well as the original configuration as radiation shield excepting gamma flux at two points. Using gamma map by MCNPX, it was checked that is distribution of gamma. Increased flux had direction to the top and it had longer distance from top of segmented shield. However, because of reducing the 35% of the height, height of dissipated gamma was lower than original geometry. Reducing the 35% of the height of the segmented shield and locating lead 10cm from the bottom of the top cover was selected. After changing geometry, radiation dose was measured by TLD for confirming tester's safety at any condition. Neutron(0.21 ${\mu}Svhr^{-1}$) and gamma(3.69 ${\mu}Svhr^{-1}$) radiation dose were satisfied standard(6.25 ${\mu}Svhr^{-1}$).

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.547-552
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• 1996

확률론적 방법을 이용한 MCNP4A 전산코드를 이용하여 두꺼운 차폐체내에서 효과적인 분산감소기법에 대하여 가장 단순화된 모델을 이용하여 고찰하여 보았다. 등방점선원과 이를 둘러싼 반경 50cm의 납차폐체를 계산을 위한 모빌로 사용하여 차폐체 내부 각 영역과 외부에서의 평균선속을 계산하였다. 분산감소기법으로는 구역분할법과 Exponential transform을 적용하여 각 구역에서의 분산의 변화를 비교하였다. 계산결과 두꺼운 차폐체문제에서는 exponential transform이 가장 효과적인 분산감소기법으로 나타났고 이때 구역분할법을 통하여서는 상대오차의 크기를 더욱 줄일 수 있었다.