• Journal of the Korean Society of Radiology
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• v.14 no.4
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• pp.425-431
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• 2020

When a radiation generating device is installed in an export container due to COVID-19, the purpose of this study was to measure the space dose in the radiation room and to study the effectiveness of the shielding wall in the laboratory. Air dose measurement method was set behind the X-ray tube, 50 cm, 100 cm, 200 cm, and measured 12 locations. The dose values before and after the use of the movable radiation shielding wall were compared by measuring 3 locations behind the X-ray tube using the movable radiation shielding wall. The measured values were 50 cm on the left behind the X-ray tube: 1.446 μSv, behind the X-ray tube: 0.545 μSv, and 50 cm on the right behind the X-ray tube: 1.466 μSv. Measurements behind the radiation barrier were 0.190 μSv, 0.204 μSv, and 0.191 μSv. As a result of performing the corresponding sample t test of the average value according to the use of movable barrier walls, p <0.001 was found. As a result of the actual measurement, the medical exposure of the examiner due to the shielding wall in the laboratory decreased to 82.3%. In order to reduce occupational exposure in screening radiological laboratories, it is recommended that sufficient separation from radiation sources and the use of shielding walls are recommended.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.347-348
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• 2004

차세대관리 종합공정 실증시설의 핫셀 차폐벽은 중량콘크리트 재질로서 외벽의 두께는 90cm 이상으로 설계되었으며, 차폐벽의 모든 부위는 이와 동일한 차폐능을 확보하도록 하여야 한다. 그러나 핫셀 운영을 위하여 불가피하게 설치되는 여러 가지 부속 시설물들에 의하여 원래 계획한 핫셀 차폐벽의 차폐능 저하를 가져오게 되며, 이런 부속 시설물로는 차폐 출입문, 방사성 물질을 핫셀 내부로 반입하거나 반출하기 위한 수송용기 접합부, 소형물 투입구, 슬리브 및 매설관등이 있다.(중략)

• Proceedings of the Materials Research Society of Korea Conference
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• 2003.11a
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• pp.228-228
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• 2003

차세대관리 종합공정에서 취급되는 기준 방사선원은 경수로에서 배출된 우라늄-235 농축도 3.5 wt%, 연소도는 43 Gwd/tU 이며 냉각기간은 10년인 사용후핵연료이다. 사용후핵연료의 기준 사양과 차세대관리 종합공정의 특성에 따라 최대 1,385 TBq의 방사선원이 핫셀내에 존재하게 되며, 핫셀 차폐벽은 총 방사능량에 대한 차폐능을 가져야 한다. 최대 방사선원에 대한 핫셀 차폐벽의 중성자에 대한 차폐능을 평가하기 위하여, 본 연구에서는 ORIGEN-2 코드를 이용하여 사용후핵연료에서 발생하는 핵종 및 핵종량을 평가하였으며, 이 자료를 기초로 하여 중성자 선원항을 SOURCES코드를 이용하여 계산하였다.

• The Journal of the Korea Contents Association
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• v.16 no.10
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• pp.758-765
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• 2016

This study analyzed for the radioactive shielding wall, which shields the medical linear accelerator. This allows to evaluate the level of waste with respect to the shield wall, which accounts for more than half of the cost of dismantling later linac facility. In addition, by analyzing the waste processing method according we discuss the way to obtain the benefits in terms of dismantling cost. Results of the simulate, the amount sufficient to screen the amount of neutron radiation occurring in the shielding wall linac was measured. And neutron activation analysis results were analyzed nuclides more than about 20. This analysis was in excess of that, $^{24}Na$, $^{45}Ca$, $^{59}Fe$ nucleus paper deregulation concentration. The value is reduced is greater the deeper the depth of the shielding wall concentration. Based on this, three specific areas (E, F, G) was estimated to be impossible to landfill or recycling. The rest area was estimated to be buried or recycled if possible more than a predetermined depth.

• Journal of radiological science and technology
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• v.39 no.1
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• pp.89-97
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• 2016

As previous studies to proceed with the evaluation of the radioactive at linear accelerator's shielding concrete wall. And the shielding wall was evaluated the characteristics for the incoming neutron. As a result, the shielding wall is the average amount of incoming neutrons 10 MV 4.63E-7%, 15 MV 9.69E-6%, showed the occurrence of 20 MV 2.18E-5%. The proportion of thermal neutrons of which are found to be approximately 18-33%. The neutron generation rate can be seen as a slight numerical order. However, in consideration of the linear accelerator operating time we can not ignore the effects of neutrons. Accordingly radioactive problem of the radiation shield wall of the treatment room will be this should be considered.

• The Journal of the Korea Contents Association
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• v.17 no.9
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• pp.69-76
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• 2017

This study evaluated the activation of the shielding wall and the components around the accelerator by using the medical linear accelerator. We performed simulations for energy values of 20 MV with the operating time ranging from day 1 to 30 years, and linear accelerator head and shielding wall concrete were also evaluated. The results showed that neutrons in large quantities were analyzed using high energy around thetarget point where photons were formed. Based on the activation analysis with these results, radioactivity increased with an increase in operation time and activated nuclides usually start saturating in10 years. Furthermore, the general types of nuclides formed owingto the activation were Co-60, W-181, 185, 187, Na-24, Ca-45, Mn-54, 56, and Fe-55, 59.

• Journal of radiological science and technology
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• v.40 no.2
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• pp.281-287
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• 2017

The purpose of this study is to calculate the thickness of shielding for concrete which is mainly used for radiation shielding and study of the walls constructed to shield medical linear accelerator. The optimal shielding thickness was calculated using MCNPX(Ver.2.5.0) for 10 MV of photon beam energy generated by linear accelerator. As a result, the TVL for photon shielding was formed at 50~100 cm for pure concrete and concrete with Boron+polyethylene at 80~100 cm. The neutron shielding was calculated 100~140 cm for pure concrete and concrete with Boron+polyethylene at 90~100 cm. Based on this study, the concrete is considered to be most efficient method of using steel plates and adding Boron+polyethylene th the concrete.

• Progress in Medical Physics
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• v.15 no.4
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• pp.247-254
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• 2004

According to developing high energy linear accelerators and treatment methods, like (3 dimensional conformal radiotherapy (3D-CRT), intensity modulated radiotherapy (IMRT), many radiotherapy centers are replacing older linear accelerators with new higher technical machines. This often presents a shielding problem as the designed shield for the existing rooms is not adequate for the higher technical machines. Additional shielding in limited existing space becomes necessary. We are replacing older brachytherapy room with new higher technical linear accelerator for IMRT. This room is not adequate for the IMRT machine without additional shielding design. The logical development of optimum structural shielding designs with concrete and high density shielding blocks are presented. We obtained following results by comparison between the pre-calculating values and actual survey of completed LINAC installation. High density shielding blocks have more powerful radiation protection about 2 times.

• Proceedings of the Korean Vacuum Society Conference
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• 2016.02a
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• pp.202-202
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• 2016

홀 플라즈마 엔진은 인공위성의 궤도유지 및 자세제어 등의 임무수행이나 우주선의 심우주 활용에 있어 필수적인 핵심 우주 부품이다. 홀추력기 연구개발의 최근 큰 관심사는 추력기의 장시간 운전성 확보 및 방전효율 향상이다. 최근 고리형 홀추력기에서 방전 영역 내 플라즈마와 유전체 벽 간의 충돌을 줄임으로써 전극 손상 및 전자온도 손실을 감소시키기 위한 연구가 활발히 진행되고 있다. 특히 전자석 코일을 활용해 방전 채널 벽면과 평행한 방향의 자기장을 형성하여 플라즈마와 유전체 벽 간의 상호작용을 감소시키는 연구들이 소개되고 있으며, 이러한 방법을 자기차폐(magnetic shielding)라 한다. 본 연구에서는 자기차폐 개념이 적용된 방전 소모전력 500 W급 고리형 홀추력기의 방전 및 추력 발생 특성을 연구하였다. 자기장구조 제어를 통해 유전체 벽과 플라즈마 간 상호작용을 감소시킨 결과, 500 V 수준의 방전 전압에서도 유전체 벽에서의 이차전자 발생에 의한 방전전류의 급격한 증가없이 안정적인 방전이 가능하였으며, 이러한 방전 형태는 기존의 자기차폐 개념이 적용되지 않은 일반 고리형 홀 추력기에서 구현하기 어려운 방전 상태이다. 추력기의 자기장 구조 최적화 조건에서 제논 가스 방전을 통해 얻은 최대 추력은 $22{\pm}1mN$, 비추력 $2200{\pm}70s$, 양극효율 $51{\pm}2%$로 매우 우수한 성능을 보여 주었다

• Applied Chemistry for Engineering
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• v.25 no.3
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• pp.268-273
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• 2014

In this study, multi-walled carbon nanotubes (MWCNT) were treated with nickel by electroless plating method for improving electromagnetic interference (EMI) shielding performance of MWCNT. The physical properties of electroless plated MWCNT were analyzed by using ultra-high resolution scanning electron microscope (UHR-SEM), thermogravimetry (TGA), sheet resistance analyzer and EMI shielding analyzer. EMI shielding efficiencies of nickel electroless plated MWCNT were measured to be 16 dB from 800 MHz band, which was 1.6 times increased compared to that of the activated MWCNT. Also, the average sheet resistance of nickel electroless plated MWCNT was measured to be $70{\Omega}/sq$, which was 56% decreased compared to that of the activated MWCNT. This result could be attributed to the plating morphology on the surface of MWCNT. This result could be attributed to uniformity of plating morphology on the surface, which has more effect on EMI shielding efficiency than the amount of nickel plating.