• Proceedings of the Korean Nuclear Society Conference
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• 1996.11b
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• pp.769-774
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• 1996

DUPIC 공정은 재처리공정과는 달리 공정의 전ㆍ후를 통하여 사용후핵연료의 양이 변하지 않기 때문에 시설이 원활히 운전되기 위해서는 사용후핵연료가 결손 또는 전용되지 않았음을 증명할 수 있어야 한다. 따라서, 핵투명성(nuclear transparency)을 보장할 수 있는 DUPIC 핵연료 보장조치용 비파괴측정 장치의 개발이 요구되었으며 $^3$He tube, 폴리에칠렌(CH$_2$)감속재, 텅스텐 차폐체 그리고 PSR(portable shift register) 등으로 구성된 측정 시스템을 제작하였다. 본 장치를 사용하여 사용후핵연료에서 검출되는 중성자중에서, $^{244}$ Cm의 자발핵분열중성자 수를 분석할 수 있으며 이를 이용하여 사용후핵연료를 계량관리 할 수 있다. 현재 측정시스템에 대한 성능시험등을 수행하고 있는 중이며 향후 DUPIC 연구용 고준위방사성물질취급시설(hot-cell)에 설치할 예정이다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.350-355
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• 1997

가압중수로(PHWR)형 원자력발전소의 저장수조에 보관중인 사용후핵연료를 대상으로 하는 핵물질 보장조치(safeguards) 이행에 필요한 핵연료다발 수중검증장치를 개발하였다. 본 장치는 CdTe 감마선검출기, 차폐체 및 시준기등으로 구성된 검출부와 이를 지지 및 구동하기 위한 구동부로 구성되어 있다. 검출부에 대하여 감마선 표준선원 및 사용후핵연료 시료를 사용하여 성능시험을 수행한 결과 현장검증시의 요건을 만족하였고, 구동부의 경우 건식조(dry pit)에서 수행한 예비실험 결과 검증목적에 적합하였다. 따라서, PHWR형 원자력발전소인 월성 1 호기의 수중저장조에 있는 사용후CANDU핵연료에 대한 현장성능시험을 현재 준비중에 있으며 그 결과를 바탕으로 하여 국가사찰시에 본 장치를 사용할 예정이며, 향후 IAEA의 공인을 획득하여 IAEA 사찰용 장비로도 활용할 계획이다.

• Proceedings of the Optical Society of Korea Conference
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• 2003.02a
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• pp.82-83
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• 2003

일반적인 PDP (Plasma display panel)용 전도성 저방출(low-e) 필터는 유리 기판 위에 굴절률이 높은 금속 산화물 유전체 박막과 Ag와 같은 귀금속 박막이 번갈아 쌓인 [유전체｜금속(Ag)｜유전체]가 기본 구조인 다층 박막의 형태로 개발되어 왔다. Ag는 가시광선 영역에서 다른 금속보다 작은 흡수를 보이고 전도성이 뛰어나 전자파 차페용 필터의 전도성 박막으로 널리 쓰인다. 그리고 이러한 구조에서 가시광선의 높은 투과율을 유지하면서 유해 전자기파를 차폐할 수 있도록 충분한 전도성을 갖추기 위해서는 2층 이상의 Ag 박막이 존재하도록 설계되며 유전체 박막과 금속 박막 사이에 1∼2 nm 정도의 매우 얇은 금속 보호 층을 사용한다. (중략)

• Journal of radiological science and technology
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• v.41 no.2
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• pp.129-134
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• 2018

The present study made a phantom for gamma ray of 140 keV radiated from $^{99m}Tc$, examined shielding effect of lead by thickness of the shielding material, and measured surface dose and depth dose by body depth. The OSL Nano Dot dosimeter was inserted at 0, 3, 15, 40, 90, and 180 mm depths of the phantom, and when there was no shield, 0.2 mm lead shield, 0.5 mm lead shield, The depth dose was measured. Experimental results show that the total cumulative dose of dosimeters with depth is highest at 366.24 uSv without shield and lowest at 94.12 uSv with 0.5 mm lead shield. The shielding effect of 0.2 mm lead shielding was about 30.18% and the shielding effect of 0.5 mm lead shielding was 74.30%, when the total sum of the accumulated doses of radiation dosimeter was 100%. The phantom depth and depth dose measurements showed the highest values at 0 mm depth for all three experiments and the dose decreases as the depth increases. This study proved that the thicker a shielding material, the highest its shielding effect is against gamma ray of 140 keV. However, it was known that shielding material can't completely shield a body from gamma ray; it reached deep part of a human body. Aside from the International Commission on Radiation Units and Measurements (ICRU) recommending depth dose by 10 mm in thickness, a plan is necessary for employees working in department of nuclear medicine where they deal with gamma ray, which is highly penetrable, to measure depth dose by body depth, which can help them manage exposed dose properly.

• Journal of radiological science and technology
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• v.43 no.4
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• pp.259-264
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• 2020

Radiation causes radiation hazards in the human body. In Korea, a case of radiation necrosis occurred in 2014. In this study, the scatter and shielding efficiency according to lead shielding were classified into epidermis and dermis for 0.511 MeV used in nuclear medicine. In this study, experiments were conducted using the slab phantom that represents calibration and the dose of human trunk. Experimental results showed that the shielding rate of 0.25 mmPb was 180% in the epidermis and 96% in the dermis. Shielding at 0.5mmPb showed shielding rates of 158%in the epidermis and 82% in the dermis. As a result of measuring the absorbed dose by subdividing the thickness of the dermis into 0.5 mm intervals, when the shielding was carried out at 0.25 mmPb, the dose appeared to be about 120% at 0.5 mm of the dermis surface, and the dose was decreased at the subsequent depth. Shielding at 0.5 mmPb, the dose appeared to be about 101% at the surface 0.5 mm, and the dose was measured to decrease at the subsequent depth. This result suggests that when lead aprons are actually used, the scattering rays would be sufficiently removed due to the spaces generated by the clothes and air, Therefore, the scattered ray generated from lead will not reach the human body. The ICRU defines the epidermis (0.07), in which the radiation-induced damage of the skin occurs, as the dose equivalent. If the radiation dose of the dermis is considered in addition, it will be helpful for the evaluation of the prognosis for radiation hazard of the skin.

• Journal of the Korean Society of Radiology
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• v.15 no.7
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• pp.965-973
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• 2021

Since radiation therapy is irradiated with high-energy X-rays in a variety of at least 20 Gy to 80 Gy, a high dose is administered to the local area where the tumor is located, and various side effects of some normal tissues are expected. Currently, in clinical practice, lead, a representative material, is used as an effort to shield normal tissues, but lead is classified as a heavy metal harmful to the human body, and a large amount of skin contact can cause poisoning. Therefore, this study intends to manufacture a measurement sheet that can compensate for the limitations of lead using the materials Tungsten, Brass, and Copper of the 3D printer of the FDM (Fused Deposition Modeling) method and to investigate the penetration performance. Tungsten mixed filament transmission measurement sheet size was 70 × 70 mm and thickness 1, 2, 4 mm using a 3D printer, and a linear accelerator (TrueBeam STx, S/N: 1187) was measured by irradiating 100 MU at SSD 100 cm and 5 cm in water using a water phantom, an ion chamber (FC-65G), and an elcetrometer (PTW UNIDOSE), and the permeability was evaluated. As a result of increasing the measurement sheet of each material by 1 mm, in the case of Tungsten sheet at 3.8 to 3.9 cm in 6 MV, the thickness of the lead shielding body was thinner than 6.5 cm, and in case of Tungsten sheet at 4.5 to 4.6 cm in 15 MV. The sheet was thinner than the existing lead shielding body thickness of 7 cm, and equivalent performance was confirmed. Through this study, the transmittance measurement sheet produced using Tungsten alloy filaments confirmed the possibility of transmission shielding in the high energy region. It has been confirmed that the usability as a substitute is also excellent. It is thought that it can be provided as basic data for the production of shielding agents with 3D printing technology in the future.

• Journal of radiological science and technology
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• v.43 no.5
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• pp.343-351
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• 2020

This study analyzed dose reduction and quality of images through dose reduction tools and shielding board to protect sensitive eye lens in radiation during orbit CT examinations for clinical data use. During CT scans of the phantom, surface dose (CT scanner dosimetry phantom, ion chamber-3 times) and quality of image (radiosurgery head phantom, visual assessment-2 times, HU standard deviation) were evaluated using X-care which is dose reduction tools and bismuth shielding board. The results of experiments of eight conditions showed a relatively reduced dose in all other conditions compared to when no conditions were set. In particular, the area corresponding to the ophthalmic part reduced the surface dose by up to 45.7 %. The visual evaluation of images by specialists and the quality evaluation of images analyzed by HU standard deviation were clinically closest to the use of X-care and shielding board (1 cm in height). Therefore, it is believed that the use of shielding board in a suitable location with dose reduction tools while investigating the optimal radiation dose will reduce the exposure dose of sensitive lens at radiation while maintaining the quality of the images with high diagnostic value.

• Aerospace Engineering and Technology
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• v.12 no.1
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• pp.46-53
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• 2013

In this study, the analysis of electromagnetic environment of goheung aviation center was performed. If the test object has restrictions to be tested in indoor test facility, open area test site can be used to perform EMC test. Open area test site shall have no obstacles that can generate or reflect the electric field so as to prevent the measurement result from being influenced by unnecessary field. Goheung aviation center is surrounded by fields, and has no buildings that can reflect electric field, so the center can be a good candidate for open area test site. Ambient noise at Goheung aviation center was measured, and the result show that the center has good electromagnetic environment to perform EMC test for large volume object.

• Radiation Oncology Journal
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• v.9 no.2
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• pp.343-350
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• 1991

The quasi-conformation therapy was performed to get a homogeneous dose distributions for irregeular shaped tumor lesion by using the arc moving beam and beam modifying filter which was made by cerrobend alloy($\rho$=9.4 g/cc) metal. In our dose calcuation programme, it was fundmentally based on Clarkson's method to calcuate the irregular multi-step block field in rotation therapy. In this study, the expected relative depth doses under multipartial attenuator agree well with measured data at same plane. The results of comparison the dose computation with that of TLD measurement are very closed within ${\pm}5\%$ uncertainties in the irradiation to phantom with quasi-comformation method. And it has shown that irregular typed multi-step filter can be applied to quasi-conformation therapy in high energy radiation plannings.

• Journal of the Korean Society of Radiology
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• v.17 no.4
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• pp.557-564
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• 2023

In this study, 3D printing technology was used to compensate for the shortcomings of the use of lead, which has proven to have excellent shielding performance, and to control unnecessary human exposure. 3D printers can implement three-dimensional shapes and can immediately apply individual ideas, which has great advantages in maintaining technology supplementation while reducing the cost and duration of prototyping. Among the various special 3D printers, the FDM method was adopted, and the filament used for output was manufactured using a research extruder by mixing two materials, PLA (Poly-Lactic-Acid) and tungsten. The purpose was to verify the validity through dose evaluation and to provide basic information on the production of chapezones of various materials. The mixed filament was implemented as a morphological shield. Filaments made of a research extruder by mixing PLA and tungsten were divided into 10 %, 20 %, 30 %, 40 %, and 50 % according to the tungsten content ratio. Through the process of 3D Modeling, STL File storage, G-code generation, and output, 10 cm × 10 cm × 0.5 cm was manufactured, respectively, and dose and shielding ability were evaluated under the conditions of tube voltages of 60 kVp, 80 kVp, 100 kVp, 120 kVp, and tube currents of 20 mAs and 40 mAs.