• Title/Summary/Keyword: 방사선 차폐

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실리콘고무계 및 에폭시수지계 차폐재의 방사선 영향에 관한 연구

  • 조수행;김익수;신영준;도재범;노성기
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05b
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    • pp.231-236
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    • 1997
  • 방사성물질의 수송 및 저장용기 등에 사용되는 실리콘고무계 및 수소 첨가된 비스페놀-A형 에폭시수지계 중성자 차폐재들의 인장강도, 압축강도, 비중, 무게, 수소함량 등에 방사선이 미치는 영향을 검토하였다. 방사선 조사선량의 증가에 따라 실리콘고무계 중성자 차폐재(KNS-101 및 102)들의 인장강도, 압축강도, 비중 등이 증가하는 경향을 나타내었으며, 차폐재의 무게는 거의 변화가 없었으나, 수소함량은 약간 감소하는 경향을 나타내었다. 또한 에폭시수지계 중성자 차폐재(KNS-201 및 202)들의 인장강도 및 압축강도는 0.1 MGy까지는 방사선 조사선량의 증가에 따라 증가하다가 0.1MGy 이상에서는 감소하는 경향을 나타내었으며, 조사선량의 증가에 따른 차폐재들의 비중, 무게 및 수소함량은 크게 변하지 않는 것으로 나타났다.

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Evaluation of Metal Composite Filaments for 3D Printing (3D 프린팅용 금속 입자 필라멘트의 물성 및 차폐 능력 평가)

  • Park, Ki-Seok;Choi, Woo-Jeon;Kim, Dong-Hyun
    • Journal of the Korean Society of Radiology
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    • v.15 no.5
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    • pp.697-704
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    • 2021
  • It is hard to get Filaments which are materials of the 3D printing Fused Deposition Modeling(FDM) method as radiation shielding in Korea. and also related research is insufficient. This study aims to provide basic data for the development of radiation shields using 3D printing by evaluating the physical properties and radiation shielding capabilities of filaments containing metal particles. after selecting five metal filaments containing metal particle reinforcement materials, the radiation shielding rate was calculated according to the Korean Industrial Standard's protective equipment test method to evaluate physical properties such as tensile strength, density, X-ray Diffraction(XRD), and weight measurement using ASTM's evaluation method. In the tensile strength evaluation, PLA + SS was the highest, ABS + W was the lowest, and ABS + W is 3.13 g/cm3 which value was the highest among the composite filaments in the density evaluation. As a result of the XRD, it may be confirmed that the XRD peak pattern of the particles on the surface of the specimen coincides with the pattern of each particle reinforcing material powder metal, and thus it was confirmed that the printed specimen contained powder metal. The shielding effect for each 3D printed composite filament was found to have a high shielding rate in proportion to the effective atomic number and density in the order of ABS + W, ABS + Bi, PLA+SS, PLA + Cu, and PLA + Al. In this study, it was confirmed that the metal particle composite filament containing metal powder as a reinforcing material has radiation shielding ability, and the possibility of using a radiation shielding filament in the future.

Research on Radiation Shielding Film for Replacement of Lead(Pb) through Roll-to-Roll Sputtering Deposition (롤투롤 스퍼터링 증착을 통한 납(Pb) 대체용 방사선 차폐필름 개발)

  • Sung-Hun Kim;Jung-Sup Byun;Young-Bin Ji
    • Journal of the Korean Society of Radiology
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    • v.17 no.3
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    • pp.441-447
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    • 2023
  • Lead(Pb), which is currently mainly used for shielding purposes in the medical radiation, has excellent radiation shielding functions, but is continuously exposed to radiation directly or indirectly due to the harmfulness of lead itself to the human body and the inconvenience caused by its heavy weight. Research on shielding materials that are human-friendly, lightweight, and convenient to use that can block risks and replace lead is continuously being conducted. In this study, based on the commonly used polyethylene terephthalate (PET) film and the fabric material used in actual radiation protective clothing, a multi-layer thin film was realized through sputtering and vacuum deposition of bismuth, tungsten, and tin, which are metal materials that can shield radiation. Thus, a shielding film was produced and its applicability as a radiation shielding material was evaluated. The radiation shielding film was manufactured by establishing the optimized conditions for each shielding material while controlling the applied voltage, roll driving speed, and gas supply amount to manufacture the shielding film. The adhesion between the parent material and the shielding metal thin film was confirmed by Cross-cut 100/100, and the stability of the thin film was confirmed through a hot water test for 1 hour to measure the change of the thin film over time. The shielding performance of the finally realized shielding film was measured by the Korea association for radiation application (KARA), and the test conditions (inverse wide beam, tube voltage 50 kV, half layer 1.828 mmAl) were set to obtain an attenuation ratio of 16.4 (initial value 0.300 mGy/s, measured value 0.018 mGy/s) and damping ratio 4.31 (initial value 0.300 mGy/s, measured value 0.069 mGy/s) were obtained. by securing process efficiency for future commercialization, light and shielding films and fabrics were used to lay the foundation for the application of films to radiation protective clothing or construction materials with shielding functions.

A Study on the Safety of a Screening X-ray Laboratory Using Containers in accordance with the COVID 19 Outbreak (COVID 19 유행에 따른 컨테이너를 이용한 선별 X-선 검사실의 안전성에 대한 고찰)

  • Kim, Jae-Seok
    • 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.

Study on Shielding using CT Contrast Medium (CT 조영제를 이용한 차폐체에 대한 연구)

  • Gang, Heon-Hyo;Kim, Dong-Hyun
    • Journal of the Korean Society of Radiology
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    • v.12 no.5
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    • pp.693-698
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    • 2018
  • Currently, shields for shielding medical radiation during medical examinations in the medical environment are lead robe and lead glass. Lead, the main component of this shielding, has limitations in lead poisoning and light weight, and high price. Iodine, which is used as contrast medium instead of lead shield, is expected to be effective as a shield because it has radiation absorbing properties. The purpose of this study was to evaluate the effectiveness of shielding by using acrylic plate filled with CT contrast agent for clinical use instead of conventional lead glass. As a result, it was found that the acrylic plate filled with the CT contrast agent showed a shielding effect of 7 times or more when the scattering ray dose was not shielded. Therefore, CT contrast agent composed of iodine is expected to be used as a shield instead of conventional lead glass.

Analysis of a Lead Vest Dose Reduction Effect for the Radiation Field at Major Working Places during Refueling Outage of Korean PWR Nuclear Power Plants (국내 가압경수로형 원전 계획예방정비기간 주요 방사선작업에 대한 납 차폐복 선량저감효과 분석)

  • Kim, Jeong-In;Lee, Byoung-Il;Lim, Young-Khi
    • Journal of Radiation Protection and Research
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    • v.38 no.4
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    • pp.237-241
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    • 2013
  • The gamma energy distributions at the major working places during refueling outage of Korean PWR nuclear power plants were measured. In order to estimate the dose reduction effect of a lead vest, Monte Carlo calculation method was used. For the simulations, the MIRD-V phantom with a lead vest was formed and exposed to the measured radiation field. The average measured gamma energy is lower than that of standard which is generally applied to radiation protection procedures. For the efficient use of a lead vest and achievement of radiation protection purpose, it is necessary to estimate the energy distribution of radiation field at working places.

Development and Performance Evaluation of X-Ray Shields using Fe2O3 and Al2O3 (산화철, 알루미나를 이용한 X선 차폐체 개발 및 성능 평가)

  • Hui-Su, Yang;Ji-Hwan, Kim;Min-Cheol, Jeon
    • Journal of Advanced Technology Convergence
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    • v.1 no.2
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    • pp.19-25
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    • 2022
  • It is intended to evaluate the performance of the shield after manufacturing a shield with cheap and eco-friendly iron oxide and alumina instead of lead, which is a radiation shielding material. After manufacturing the shield by mixing iron oxide and alumina with gypsum, the performance is evaluated by comparing it with gypsum board and lead apron using an X-ray tube. As a result of the experiment, the shielding performance of alumina was lower than that of the gypsum board, and when 50% of alumina was contained, the shielding performance was similar to that of the gypsum board. Iron oxide became similar to the shielding performance of lead apron when it contained about 75%. A shielding material using alumina shows shielding performance similar to that of gypsum, so it is not suitable as a substitute for lead. However, since iron oxide exhibits similar shielding performance to lead, it can be used as an X-ray shielding material to replace lead in the future, so further research is needed.

An Analysis of Exposure Dose on Hands of Radiation Workers using a Monte Carlo Simulation in Nuclear Medicine (몬테카를로 모의 모사를 이용한 핵의학과 방사선작업종사자의 손에 대한 피폭선량 분석)

  • Jang, Dong-Gun;Kang, Sesik;Kim, Junghoon;Kim, Changsoo
    • Journal of radiological science and technology
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    • v.38 no.4
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    • pp.477-482
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    • 2015
  • Workers in nuclear medicine have performed various tasks such as production, distribution, preparation and injection of radioisotope. This process could cause high radiation exposure to wokers' hand. The purpose of this study was to investigate shielding effect for r-rays of 140 and 511 keV by using Monte-carlo simulation. As a result, it was effective, regardless of lead thickness for radiation shielding in 140 keV r-ray. However, it was effective in shielding material with thickness of more than only 1.1 mm in 511keV r-ray. And also it doesn't effective in less than 1.1 mm due to secondary scatter ray and exposure dose was rather increased. Consequently, energy of radionuclide and thickness of shielding materials should be considered to reduce radiation exposure.