• 제목/요약/키워드: NCRP 49 report

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Review of Shielding Evaluation Methodology for Facilities Using kV Energy Radiation Generating Devices Based on the NCRP-49 Report

  • Na Hye Kwon;Hye Sung Park;Taehwan Kim;Sang Rok Kim;Kum Bae Kim;Jin Sung Kim;Sang Hyoun Choi;Dong Wook Kim
    • 한국의학물리학회지:의학물리
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    • 제33권4호
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    • pp.53-62
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    • 2022
  • In this study, we have investigated the shielding evaluation methodology for facilities using kV energy generators. We have collected and analysis of safety evaluation criteria and methodology for overseas facilities using radiation generators. And we investigated the current status of shielding evaluation of domestic industrial radiation generators. According to the statistical data from the Radiation Safety Information System, as of 2022, a total of 7,679 organizations are using radiation generating devices. Among them, 6,299 facilities use these devices for industrial purposes, which accounts for a considerable portion of radiation. The organizations that use these devices evaluate whether the exposure dose for workers and frequent visitors is suitable as per the limit regulated by the Nuclear Safety Act. Moreover, during this process, the safety shields are evaluated at the facilities that use the radiation generating devices. However, the facilities that use radiating devices having energy less than or equal to 6 MV for industrial purposes are still mostly evaluated and analyzed according to the National Council on Radiation Protection and Measurements 49 (NCRP 49) report published in 1976. We have investigated the technical standards of safety management, including the maximum permissible dose and parameters assessment criteria for facilities using radiation generating devices, based on the NCRP 49 and the American National Standards Institute/Health Physics Society N.43.3 reports, which are the representative reports related to radiation shielding management cases overseas.

X선촬영실의 콘크리트 방어벽 두께 계산에 관한 연구 (A Study on Calculation of the Thickness of Concrete Protective Barrier of X-ray Radiographic Room)

  • 박철서
    • 대한방사선기술학회지:방사선기술과학
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    • 제33권4호
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    • pp.363-367
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    • 2010
  • 본 연구의 목적은 X-선촬영장치의 1차방어벽두께 계산에 관한 쉬운 방법의 연구이다. X-선촬영장치에 대한 1차방어벽의 두께 계산을 위하여, 차폐물질은 콘크리트를 선택하였다. 방어벽의 구역들은 관리구역과 비관리구역으로 분류하였다. 두께의 계산은 NCRP 보고서 49와 51의 데이터를 사용하였다. 최대관전압 100과 150 kVp를 갖는 X-선촬영장치들에 대하여, 콘크리트 두께들은 거리의 함수로서 계산되었다. 계산된 데이터로부터, 식 (3), (4), (5), 그리고 (6)은 지수감소함수의 정합을 수행하여 얻었다. 본 연구에서 얻어진 수식들로부터, 1차방어벽의 두께는 근사적으로 계산할 수 있다.

Preliminary study for the development of radiation safety evaluation methodology for industrial kV-rated radiation generator facilities

  • Hye Sung Park ;Na Hye Kwon ;Sang Rok Kim ;Hwidong Yoo;Jin Sung Kim ;Sang Hyoun Choi;Dong Wook Kim
    • Nuclear Engineering and Technology
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    • 제55권10호
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    • pp.3854-3859
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    • 2023
  • Background: This study aims to develop an evaluator that can quickly and accurately evaluate the shielding of low-energy industrial radiation generators. Methods: We used PyQt to develop a graphical user interface (GUI)-based program and employed the calculation methodology reported in the National Council on Radiation Protection and Measurements (NCRP)-49 for shielding calculations. We gathered the necessary factors for shielding evaluation using two libraries designed for Python, pandas and NumPy, and processed them into a database. We verified the effectiveness of the proposed program by comparing the results with those from safety reports of six domestic facilities. Results: After verifying the effectiveness of the program using the NCRP-49 example, we obtained an average error rate of 1.73%. When comparing the facility safety report and results obtained using the program, we found that the error rate was between 1.09% and 6.51%. However, facilities that did not use a defined shielding methodology were underestimated by 31.82% compared with the program (the final barrier thickness satisfied the shielding standard). Conclusion: The developed program provides a fast and accurate shielding evaluation that can assist personnel that work in radiation generator facilities and government officials in reviewing safety.

진단 영역의 X-선 에너지에서 각종 건축재료의 감약율 측정실험 (A Experimental Study on Attenuation Rate of Construction Materials in the Diagnostic X-ray Energy)

  • 김정민;정희원
    • 대한방사선기술학회지:방사선기술과학
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    • 제21권2호
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    • pp.11-18
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    • 1998
  • Single phase, narrow beam X-ray attenuation data were obtained using various construction materials concrete, white block, red block, 3 hole block, gypsum board, artificial marble, cement, plate glass, wood, and lead. Tube voltages of 60, 80, 100, 120 kVp were employed and the resulting curves were compared to transmission data found in this report. The shielding methodology and the derivation of equations used for determination of barrier requirements were presented in NCRP 49. We could calculate the X-ray exposed dose after attenuation and thickness of protection barrier in the clinic facilities accordingly. For the purpose of maximizing the benefit/cost ratio to diagnostic shielding, various construction materials must be installed carefully and attnuation rate considered thoroughly.

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