• 제목/요약/키워드: Portable radiation survey meter

검색결과 6건 처리시간 0.026초

이동형 X-ray 발생장치를 이용한 복부 촬영 시 공간 선량률에 관한 연구 (Analysis of Space Radiation Dose Rate using portable X-ray Generating Device for Abdomen)

  • 박창희
    • 대한디지털의료영상학회논문지
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    • 제12권2호
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    • pp.97-101
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    • 2010
  • This experimental study is carried out one of the General Hospital in Kyungbok providence. Abdomen Phantom being located Anterior-posterior(AP) position on portable bed, and the portable X-ray generating device was placed the phantom at $-90^{\circ}$ direction. The experiment were set 65 kVp, 10 mAs, $10{\times}10\;cm^2$, 100 cm(FOD) for the measurement. Digital proportional counting tube survey meter was used for measuring the space scatter dose. Measurement points of horizontal distribution was set up at $30^{\circ}$ interval by increasing 50 cm radius of upside, downside, left and right. Vertical distribution of measurement points were set up for the vertical plane with a radius of at $30^{\circ}$ intervals with 50cm increments. It is concluded that longer distance from the soure of X-ray significantly decrease radiation dose to the patient and use of the radiation protection device should be applied in clinical practice to reduce dose to the patient.

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Improvement of accuracy in radioactivity assessment of medical linear accelerator through self-absorption correction in HPGe detector

  • Suah Yu;Na Hye Kwon;Sang-Rok Kim;Young Jin Won;Kum Bae Kim;Se Byeong Lee;Cheol Ha Baek;Sang Hyoun Choi
    • Nuclear Engineering and Technology
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    • 제56권6호
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    • pp.2317-2323
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    • 2024
  • Medical linear accelerators with an energy of 8 MV or higher are radiated owing to photonuclear reactions and neutron capture reactions. It is necessary to quantitatively evaluate the concentration of radioactive isotopes when replacing or disposing them. HPGe detectors are commonly used to identify isotopes and measure radioactivity. However, because the detection efficiency is generally calibrated using a standard material with a density of 1.0 g/cm3, a self-absorption effect occurs if the density of the measured material is high. In this study, self-absorption correction factors were calculated for tungsten, lead, copper, and SUS-303, which are the main materials of medical linear accelerator head parts, for each gamma-ray energy using MCNP 6.2 code. The self-absorption effect was more pronounced as the energy of the emitted gamma rays decreased and the density of the measured materials increased. These correction factors were applied to the radioactivity measurements of the in-built and portable HPGe detectors. Furthermore, compared to the surface dose rate measured by the survey meter, the accuracy of the measurements of radioactivity improved by an average of 124.31 and 100.53 % for inbuilt and portable HPGe detectors, respectively. The results showed a good agreement, with an average difference of 3.70 and 5.24 %.

Current status of disposal and measurement analysis of radioactive components in linear accelerators in Korea

  • Kwon, Na Hye;Shin, Dong Oh;Kim, Jinsung;Yoo, Jaeryong;Park, Min Seok;Kim, Kum Bae;Kim, Dong Wook;Choi, Sang Hyoun
    • Nuclear Engineering and Technology
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    • 제54권2호
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    • pp.507-513
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    • 2022
  • When X-ray energy above 8 MV is used, photoneutrons are generated by the photonuclear reaction, which activates the components of linear accelerator (linac). Safely managing the radioactive material, when disposing linac or replacing components, is difficult, as the standards for the radioactive material management are not clear in Korea. We surveyed the management status of radioactive components occurred from medical linacs in Korea. And we also measured the activation of each part of the discarded Elekta linac using a survey meter and portable High Purity Germanium (HPGe) detector. We found that most medical institutions did not perform radiation measurements when disposing of radioactive components. The radioactive material was either stored within the institution or collected by the manufacturer. The surface dose rate measurements showed that the parts with high surface dose rates were target, primary collimator, and multileaf collimator (MLC). 60Co nuclide was detected in most parts, whereas for the target, 60Co and 184Re nuclides were detected. Results suggest that most institutions in Korea did not have the regulations for disposing radioactive waste from linac or the management procedures and standards were unclear. Further studies are underway to evaluate short-lived radionuclides and to lay the foundation for radioactive waste management from medical linacs.

Measurements of Neutron Activation and Dose Rate Induced by High-Energy Medical Linear Accelerator

  • Kwon, Na Hye;Jang, Young Jae;Kim, Jinsung;Kim, Kum Bae;Yoo, Jaeryong;Ahn, So Hyun;Kim, Dong Wook;Choi, Sang Hyoun
    • 한국의학물리학회지:의학물리
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    • 제32권4호
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    • pp.145-152
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    • 2021
  • Purpose: During the treatments of cancer patients with a linear accelerator (LINAC) using photon beams with energies ≥8 MV, the components inside the LINAC head get activated through the interaction of photonuclear reaction (γ, n) and neutron capture (n, γ). We used spectroscopy and measured the dose rate for the LINAC in operation after the treatment ended. Methods: We performed spectroscopy and dose rate measurements for three units of LINACs with a portable high-purity Germanium (HPGe) detector and a survey meter. The spectra were obtained after the beams were turned off. Spectroscopy was conducted for 3,600 seconds, and the dose rate was measured three times. We identified the radionuclides for each LINAC. Results: According to gamma spectroscopy results, most of the nuclides were short-lived radionuclides with half-lives of 100 days, except for 60Co, 65Zn, and 181W nuclides. The dose rate for three LINACs obtained immediately in front of the crosshair was in the range of 0.113 to 0.129 µSv/h. The maximum and minimum dose rates measured on weekends were 0.097 µSv/h and 0.092 µSv/h, respectively. Compared with the differences in weekday data, there was no significant difference between the data measured on Saturday and Sunday. Conclusions: Most of the detected radionuclides had half-lives <100 days, and the dose rate decreased rapidly. For equipment that primarily used energies ≤10 MV, when the equipment was transferred after at least 10 minutes after shutting it down, it is expected that there will be little effect on the workers' exposure.

반도체 제조 이온주입 공정의 이온 임플란타 장치에서 엑스레이 발생 특성 (Characterization of X-ray Emitted in the Ion Implantation Process of Semiconductor Operations)

  • 박동욱;조경이;김소연;이승희;정은교
    • 한국산업보건학회지
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    • 제33권4호
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    • pp.439-446
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    • 2023
  • Objectives: The aims of this study are to investigate how X-rays are emitted to surrounding parts during the ion implantation process, to analyze these emissions in relation to the properties of the ion implanter equipment, and to estimate the resulting exposure dose. Eight ion implanters equipped with high-voltage electrical systems were selected for this study. Methods: We monitored X-ray emissions at three locations outside of the ion implanters: the accelerator equipped with a high-voltage energy generator, the impurity ion source, and the beam line. We used a Personal Portable Dose Rate and Survey Meter to monitor real-time X-ray levels. The SX-2R probe, an X-ray Features probe designed for use with the RadiagemTM meter, was also utilized to monitor lower ranges of X-ray emissions. The counts per second (CPS) measured by the meter were estimated and then converted to a radiation dose (𝜇Sv/hr) based on a validated calibration graph between CPS and μGy/hr. Results: X-rays from seven ion implanters were consistently detected in high-voltage accelerator gaps, regardless of their proximity. X-rays specifically emanated from three ion implanters situated in the ion box gap and were also found in the beam lines of two ion implanters. The intensity of these X-rays did not show a clear pattern relative to the devices' age and electric properties, and notably, it decreased as the distance from the device increased. Conclusions: In conclusion, every gap, in which three components of the ion implanter devices were divided, was found to be insufficiently shielded against X-ray emissions, even though the exposure levels were not estimated to be higher than the threshold.

방사성폐기물 처분시설 주변의 방사선환경조사 (Radiological Environment Investigation of Radioactive Waste Disposal Facility)

  • 백정석;정의영;안상복;김완
    • 방사성폐기물학회지
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    • 제6권4호
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    • pp.387-398
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    • 2008
  • 원자력이용시설 주변의 방사선환경조사는 교육과학기술부 고시 제2008-28호(원자력이용시설 주변의 방사선환경조사 및 방사선환경 영향평가에 관한 고시)에 따라 주변주민들이 받게 되는 방사선량이 연간 선량한도 이내로 충분히 적게 유지되고 있는지를 확인함으로써 주변주민의 건강과 안전을 확보하고 주변 환경의 오염을 사전에 예방하는 데 있다. 그런데 국내 최초의 방사성폐기물처분시설은 시설운영을 시작하기 전 최소 2년 동안의 기초 환경조사 자료를 취득하여 부지주변의 기준 준위를 설정해야 하므로 2007년부터 2009년 상반기 방사성폐기물처분시설의 시범운영 및 2010년 상반기 준공을 목표로 방사선과 방사능에 대한 관한 기초 환경조사 자료를 취득하고 있다. 따라서 방사성폐기물처분시설 주변의 방사선환경조사에 관한 추진내용을 분석하고 최근에 취득한 2008년도 전반기 방사선환경조사결과를 바탕으로 향후 조사계획서 개정방향과 방사성폐기물처분시설 주변의 방사선환경조사를 수행하기 위해 관련 내용을 고찰하였다.

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