• Title/Summary/Keyword: 차폐물질

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The Analysis of the Collimator & Radiation Shield for the Radiation Sensor for the 3Dimension Radiation Detection (3차원 방사선 탐지장치용 검출센서의 차폐체 및 Collimator 구조 분석 연구)

  • Hwang, Young-Gwan;Lee, Nam-Ho;Park, Sumg-Hun;Jeong, Sang-Hun;Kim, Jong-Ryul;Choi, Myung-Jin
    • Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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    • 2014.05a
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    • pp.707-709
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    • 2014
  • The radiation sources leaked from large-scale radiation leak accident like the Fukushima nuclear power plant accident or nuclear explosions can cause to the very large damage for us. So that the damage can be minimized, we have being developed a detector that can providing information about the location of the source to remove dangerous substances quickly than the conventional single detector. In this paper, we designed and implemented the radiation shield and the collimator for the development of the stereo radiation detector to detect contamination things using MCNP Simulation. And we analysed the test results of the radiation shield and collimator using the radiation source. The results of this paper will be used as the basis for improving the efficiency of the stereo radiation detector being studied currently.

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Reduced Effect of kV-CBCT Dose by Use of Shielding Materials in Radiation Therapy (방사선 치료 시 차폐물질 사용에 따른 kV-CBCT 선량감소 효과)

  • Jo, Hyeonjong;Park, Euntae;Kim, Junghoon
    • Journal of the Korean Society of Radiology
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    • v.12 no.4
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    • pp.467-474
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    • 2018
  • CBCT is useful for improving the accuracy of the treatment site, but Repeated use increases the exposure dose. In this study, we aimed to provide basic data for dose reduction in CBCT implementation by dataization the simulating and dose reduction effect using shielding substance. Material in this study, Analyzation the photon beam by simulate the CBCT Through MCNPX and then calculate the absorption dose of body organ at shooting moment of thoracic abdominal position as target UF-Revise simulated body. At this time. Dose reduction effects at this time were evaluated according to the texture of materials and presence of shielding materials( lead, antimony, barium, sulfate, tungsten, bismuth). When CBCT was taken without shielding, the dose was calculated to be high in the breast and spine, and the dose in the esophagus and lung was calculated to be low. The doses according to the shield material were calculated as barium sulfate, antimony, bismuth, lead, and tungsten. The shielding rate was the highest in the thymus (73.6%) and the breast (59.9%) compared with the dose reduction according to presence or absence of the shield. However, it showed the lowest shielding rate in lung (2.1%) and spine (12.6%).

Evaluation of the Usefulness of Tungsten Nanoparticles as an Alternative to Lead Shielding Materials in Electron Beam Therapy (전자선 치료시 납 차폐체 대체물질로서의 텅스텐 나노입자의 유용성 평가)

  • Kim, Ji-Hyang;Kim, Na-Kyoung;Lee, Gyu-Yeong;Jung, Da-Bin;Heo, Yeong-Cheol
    • Journal of the Korean Society of Radiology
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    • v.15 no.7
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    • pp.949-956
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    • 2021
  • The purpose of this paper is to evaluate whether tungsten nanoparticles have a shielding effect on scattered light generated at high doses as an alternative material to lead used to shield scattered light in electron beam therapy. A plate was manufactured to set the position of the dosimeter and the size of the radiation field to be constant. The glass dosimeter was placed at 12 points, which were 1, 2, and 4 cm apart from the center of the field of 10 × 10 cm2 in the cross direction. A total of 12 types of tungsten nanoparticle shields were developed with a thickness of 0.75 mm to 4.00 mm and a size of 10 × 10 cm2 using 0.4, 0.75, and 1 mm materials. Using a linear accelerator, measurements were made four times at 6 MeV and four times at 12 MeV, and the dose intensity was investigated at 100 MU. The 4 mm shielding plate showed the highest shielding effect at 1 cm from the irradiation field. The 1 mm shielding plate at 2 cm from the irradiation field had the lowest shielding effect. As the thickness of the tungsten shielding plate increased, the electron beam's shielding effect increased sharply. It was confirmed that tungsten nanoparticles can reduce the amount of scattered light generated by electron beam therapy. Therefore, this study will provide basic data when follow-up studies are conducted on the shielding ability of tungsten nanoparticles.

Evaluation of Shielding Performance of 3D Printer Materials for High-energy Electron Radiation Therapy (고 에너지 전자선 치료를 위한 3D 프린터 물질의 차폐 성능평가)

  • Chang-Woo, Oh;Sang-Il, Bae;Young-Min, Moon;Hyun-Kyoung, Yang
    • Journal of the Korean Society of Radiology
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    • v.16 no.6
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    • pp.687-695
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    • 2022
  • To find a 3D printer material that can replace lead used as a shield for high-energy electron beam treatment, the shielding composites were simulated by using MCNP6 programs. The Percent Depth Dose (PDD), Flatness, and Symmetry of linear accelerators emitting high-energy electron beams were measured, and the linear accelerator was compared with MCNP6 after simulation, confirming that the source term between the actual measurement and simulation was consistent. By simulating the lead shield, the appropriate thickness of the lead shield capable of shielding 95% or more of the absorbed dose was selected. Based on the absorption dose data for lead shield with a thickness of 3 mm, the shielding performance was analyzed by simulating 1, 5, 10, and 15 mm thicknesses of ABS+W (10%), ABS+Bi (10%), and PLA+Fe (10%). Each prototype was manufactured with a 3D printer, measured and analyzed under the same conditions as in the simulation, and found that when ABS+W (10%) material was formed to have a thickness of at least 10mm, it had a shielding performance that could replace lead with a thickness of 3mm. The surface morphology and atomic composition of the ABS+W (10%) material were evaluated using a scanning electron microscope (SEM) and an energy dispersive X-ray spectrometer (EDS). From these results, it was confirmed that replacing the commercialized lead shield with ABS+W (10%) material not only produces a shielding effect such as lead, but also can be customized to patients using a 3D printer, which can be very useful for high-energy electron beam treatment.

바실러스에 의한 중금속 제거 및 EPS 추출물질 비교에 관한 연구

  • Son, Han-Hyeong;Kim, Pan-Su;Lee, Sang-Ho
    • Proceedings of the Korean Environmental Sciences Society Conference
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    • 2006.05a
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    • pp.423-427
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    • 2006
  • 1) 바실러스는 불리한 환경조건에서 포자를 형성하며 포자는 균체가 죽어도 살아 남고, 외부 환경이 좋아지면 다시 발아하여 영양형 균체를 형성하게 된다. 본 연구에서 바실러스를 우점화와 포자의 활성화를 위해 열처리(80$^{\circ}C$, 10min)를 한다 울산분뇨처리장 슬러지 Cake를 배양하여 포자화 전 후 상태의 미생물의 EPS 추출결과 RCF법을 적용하였을 때 Carbohydrate물질이 다른 추출법에 비해 가장 많이 추출되었고, Steaming extraction법을 적용하였을 때 Protein이 가장 많이 추출되는 것으로 나타났으며, 포자화 전 보다 포자화 후의 EPS 양이 더 많이 추출될 것이라는 가설을 가지고 실험한 결과 포자화 전보다 포자화 후의 EPS 양이 더 많이 추출되었다. 울산분뇨처리장의 슬러지 Cake를 배양하여 포자화 전 후의 Cu의 제거정도를 비교한 결과 포자화 후의 EPS물질이 포자화 전의 EPS물질보다 Cu를 더 많이 제거하는 것으로 나타났으며 EPS 물질이 중금속 제거능력이 탁월하다고 할 수 있겠다. 2) 용인분뇨처리장과 천안하수처리장의 MLSS의 중금속 제거능력을 알아보기 위해 미생물량을 고려했을 경우와 미생물량을 고려하지 않은 경우로 나누어서 실험을 하였는데 울산분뇨처리장의 슬러지 Cake를 가지고 실험한 결과와 마찬가지로 Bacillus의 EPS물질이 중금속 제거에 탁월하다는 것을 알 수 있다. 3) Baillus를 사용하는 김천 식품폐수 처리장과 활성슬러지를 사용하는 천안하수처리장과의 EPS 함량을 비교한 결과 김천 식품폐수 처리장의 EPS 물질중 Protein과 Carbohydrate가 천안하수처리장의 활성슬러지보다 더 많은 것으로 나타났다.TEX>, DIN/DIP비 표층수 $23.91\pm3.42$, 저층수 $23.43\pm3.38$이었으며, 전반적으로 해역별 수질기준 I등급 내지는 II등급을 유지하고 있었고, 공간적으로는 외해측으로 갈수록 외해수와 혼합 확산되어 양호한 수질을 나타내었다. 장기적인 변동특성은 세그룹으로 구분되어진다.기 실험결과 용출용매로 증류수와 해수를 이용했을 때, 제강 슬래그에서 용출되는 납, 구리, 카드뮴, 수은의 용출 경향의 차이를 확인할 수 있었고 이에 따라서, 납, 구리, 카드뮴의 용출 유해성은 낮기 때문에 해양구조물로의 제강슬래그 유효이용은 적합할 것으로 판단되었다.im80%$로 계산되었다. 열형광선량계로 측정된 방사선량은 각각 1.8, 1.2, 0.8, 1.2, 0.8 (70 cm 거리) cGy로 측정되었으며, 환자의 복부 표면에서의 서베이메터를 이용한 측정량은 10.9 mR/h였다. 차폐구조물의 사용 시 전체 치료 동안에 태아선량은 약 1 cGy 정도로 평가되었다. 결론 : AAPM Report No.50의 자료에 따르면, 임산부의 방사선 치료 시 태아의 방사선 피폭선량은 5 cGy 이하일 경우에 방사선 피폭에 따른 태아의 위험이 거의 없는 것으로 제시되고 있다. 본원에서 차폐 구조물을 설치하였을 경우에 측정된 태아선량은 약 1 cGy로 측정되었고, 고안된 차폐구조물은 태아에 도달하는 방사선량을 감소시키기에 적합한 설계임이 입증되었다. 아니라 일반종합병원에서도 CTX-M형 ESBL 생성 E. coli와 K. pneumoniae가 존재하며 확산 중임을 시사한다. 앞으로 CTX-M형 ESBL의 만연과 변종 CTX-M형 ESBL의 출연을 감시하기 위한 정기적인 연구와 조사가 필

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Shielding Calculations of Accelerator Facility for Medical Isotope Production using MCNPX Code (MCNPX 코드를 이용한 의료용 방사성동위원소 생산을 위한 가속기 시설의 방사선차폐 및 선량 계산)

  • Seo Kyu-Seok;Kim Chan-Hyeong
    • Progress in Medical Physics
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    • v.15 no.4
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    • pp.210-214
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    • 2004
  • Since production of radioactive isotope for using PET, a lot of neutrons were produced. The produced neutrons were mainly shielded by concrete facility. Secondary photons are generated and emitted from the concrete shielding wall of the PET cyclotron since the proton-generated neutrons are thermalized and absorbed in the concrete wall and emit secondary radiations, i.e., photons. This study calculated neutron dose and photon dose at outside of the accelerator facility using MCNPX code. As results of the calculation, total dose were calculated less than limited dose by law.

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Shielding Design Optimization of the HANARO Cold Neutron Triple-Axis Spectrometer and Radiation Dose Measurement (냉중성자 삼축분광장치의 차폐능 최적화 설계 및 선량 측정)

  • Ryu, Ji Myung;Hong, Kwang Pyo;Park, J.M. Sungil;Choi, Young Hyeon;Lee, Kye Hong
    • 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 ${\mu}Svhr^{-1}$).

A study on the electrostatic and magnetic flux cut off effect using anti-magnetic material (반자성 물질에 의한 전자기차단효과에 관한 연구)

  • Hwang, Yoon-Taek
    • Journal of the Korea Institute of Information and Communication Engineering
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    • v.12 no.8
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    • pp.1473-1480
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    • 2008
  • Bisumus has a low melting point, making it easier to handle. This allows us to test what type of effect diamagnetism has on electro static and magnetic field shields. However, the actual materials for experimentation have only ever been manufactured cylindrically, and so there have been no recorded cases of measurements to this effect. To understand what kind of effect pure bisumus as diamagnetism has on electro static and magnetic shields in comparison to other materials, bisumus, along with copper, aluminum and iron 스텐도, were used to make a cylinder each. These cylinders were then used to measure and compare the electro static shield and magnetic shield at different bands of frequencies, starting from a low frequency. As shown on the graph/chart/diagram, the best results were recorded for copper and bisumus as diamagnetism in an electro static field. In terms of magnetic shielding, iron provided the best results, as expected, whereas bisumus displayed minimal effect.

Reliability Verification of FLUKA Transport Code for Double Layered X-ray Protective Sheet Design (이중 구조의 X선 차폐시트 설계를 위한 FLUKA 수송코드의 신뢰성 검증)

  • Kang, Sang Sik;Heo, Seung Wook;Choi, Il Hong;Jun, Jae Hoon;Yang, Sung Woo;Kim, Kyo Tae;Heo, Ye Ji;Park, Ji Koon
    • Journal of the Korean Society of Radiology
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    • v.11 no.7
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    • pp.547-553
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    • 2017
  • In the current medical field, lead is widely used as a radiation shield. However, the lead weight is very heavy, so wearing protective clothing such as apron is difficult to wear for long periods of time and there is a problem with the danger of lethal toxicity in humans. Recently, many studies have been conducted to develop substitute materials of lead to resolve these problems. As a substitute materials for lead, barium(Ba) and iodine(I) have excellent shielding ability. But, It has characteristics emitting characteristic X-rays from the energy area near 30 keV. For patients or radiation workers, shielding materials is often made into contact with the human body. Therefore, the characteristic X-rays generated by the shielding material are directly exposured in the human body, which increases the risk of increasing radiation absorbed dose. In this study, we have developed the FLUKA transport code, one of the most suitable elements of radiation transport codes, to remove the characteristic X-rays generated by barium or iodine. We have verified the reliability of the shielding fraction of the structure of the structure shielding by comparing with the MCPDX simulations conducted as a prior study. Using the MCNPX and FLUKA, the double layer shielding structures with the various thickness combination consisting of barium sulphate ($BaSO_4$) and bismuth oxide($Bi_2O_3$) are designed. The accuracy of the type shown in IEC 61331-1 was geometrically identical to the simulation. In addition, the transmission spectrum and absorbed dose of the shielding material for the successive x-rays of 120 kVp spectra were compared with lead. In results, $0.3mm-BaSO_4/0.3mm-Bi_2O_3$ and $0.1mm-BaSO_4/0.5mm-Bi_2O_3$ structures have been absorbed in both 33 keV and 37 keV characteristic X-rays. In addition, for high-energy X-rays greater than 90 keV, the shielding efficiency was shown close to lead. Also, the transport code of the FLUKA's photon transport code was showed cut-off on low-energy X-rays(below 33keV) and is limited to computerized X-rays of the low-energy X-rays. But, In high-energy areas above 40 keV, the relative error with MCNPX was found to be highly reliable within 6 %.

Verification of Shielding Materials for Customized Block on Metal 3D Printing (금속 3D 프린팅을 통한 맞춤형 차폐블록 제작에 사용되는 차폐 재료 검증)

  • Kyung-Hwan, Jung;Dong-Hee, Han;Jang-Oh, Kim;Hyun-Joon, Choi;Cheol-Ha, Baek
    • Journal of the Korean Society of Radiology
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    • v.17 no.1
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    • pp.25-30
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    • 2023
  • As 3D printing technology is used in the medical field, interest in metal materials is increasing. The Department of Radiation Oncology uses a shielding block to shield the patient's normal tissue from unnecessary exposure during electron beam therapy. However, problems such as handling of heavy metal materials such as lead and cadmium, reproducibility according to skill level and uncertainty of arrangement have been reported. In this study, candidate materials that can be used for metal 3D printing are selected, and the physical properties and radiation dose of each material are analyzed to develop a customized shielding block that can be used in electron beam therapy. As candidate materials, aluminum alloy (d = 2.68 g/cm3), titanium alloy (d = 4.42 g/cm3), and cobalt chromium alloy (d = 8.3 g/cm3) were selected. The thickness of the 95% shielding rate point was derived using the Monte Carlo Simulation with the irradiation surface and 6, 9, 12, and 16 energies. As a result of the simulation, among the metal 3D printing materials, cobalt chromium alloy (d = 8.3 g/cm3) was similar to the existing shielding block (d = 9.4 g/cm3) in shielding thickness for each energy. In a follow-on study, it is necessary to evaluate the usefulness in clinical practice using customized shielding blocks made by metal 3D printing and to verify experiments through various radiation treatment plan conditions.