• 제목/요약/키워드: Radiation safety

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Radiation Safety Management in Dental Radiology: Present Status and Future (임상가를 위한 특집 3 - 치과방사선검사의 방사선안전관리: 국내외 현황 및 전망)

  • Kim, Eun-Kyung
    • The Journal of the Korean dental association
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    • v.52 no.3
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    • pp.147-152
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    • 2014
  • Recently the patient exposure by medical and dental x-ray examination has grown rapidly and diagnostic radiology represents the largest source of man-made radiation. For the patient protection, the principle of justification and optimization should be followed. All the radiographic examinations have to show a potential benefit to the patient weighing against the potential risk. After they are justified, the radiographic exposure should be kept as low as reasonably achievable, taking into account economic and social factors. For the safe use of radiation in dentistry, the radiation safety management in accordance with the legislation is important. The present status and the future of radiation safety management in dental radiology in Korea and other country will be discussed.

Analysis of Radiation/Radioactivity-Related Knowledge, Perception and Behaviors of Radiological Technologists (방사선사의 방사선/능에 대한 지식, 인식, 행위 분석)

  • Kim, Jung-Hoon;Ko, Seong-Jin;Kang, Se-Sik;Choi, Seok-Yoon;Kim, Chang-Soo
    • Journal of radiological science and technology
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    • v.34 no.2
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    • pp.123-129
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    • 2011
  • This study aimed at 1) investigating the perception, knowledge and behaviors of radiological technologists on radiation defence and 2) preparing plans to reduce the unnecessary radiation dose on practician, patients and their caretakers. For data collection, a structured questionnaire was used to survey 225 radiological technologists living in downtown Busan. To analyze the collected data, SPSS/PC+ Win 13 version was used. For verification of differences between groups, one-way ANOVA was conducted. In addition, multiple regression analysis was conducted to analyze the impact of general variables (knowledge, education, age and length of service) in radiation safety management perspective. No differences were found in terms of the knowledge on radiation/radioactivity according to educational background, age and length of service. In the perspective of radiation safety management, the highest figures were found among those in their 40s and higher and those with the education of college graduation and higher. As for the correlation between radiation safety management and knowledge on radiation/radioactivity, positive correlations were found in all cases. In addition, analysis on the impact of general variables in radiation safety management perspective indicated that the perception on radiation safety management was higher as the level of knowledge on radiation/radioactivity was higher. The correct radiation/radioactivity management through practician training was necessary to reduce radiation dose on radiological technologists and patients.

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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    • v.55 no.10
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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.

A Prediction Model for the Radiation Safety Management Behavior of Medical Cyclotrons (의료용 Cyclotron의 방사선안전관리 행위 예측모형)

  • Jung, Ji-Hye;Han, Eun-Ok;Kim, Ssang-Tae
    • Journal of Radiation Protection and Research
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    • v.33 no.2
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    • pp.77-86
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    • 2008
  • This study attempted to provide reference materials for improving the behavior level in radiation safety managements by drawing a prediction model that affects the radiation safety management behavior because the radiation safety management of medical Cyclotrons, which can be used to produce radioisotopes, is an important factor that protects radiation caused diseases not only for radiological operators but average users. In addition, this study obtained follows results through the investigation applied from January 2 to January 30, 2008 for the radiation safety managers employed in 24 authorized organizations, which have already installed Cyclotrons, through applying a specific form of questionnaire in which the validity was guaranteed by reference study, site investigation, and focus discussion by related experts. The radiation safety management were configured as seven steps: Step 1 is a production preparation step, Step 2 is an RI production step, Step 3 is a synthesis step, Step 4 is a distribution step, Step 5 is a quality control step, Step 6 is a carriage container packing step, and Step 7 is a transportation step. it was recognized that the distribution step was the most exposed as 15 subjects (62.5%), the items of 'the sanction and permission related works' and 'the guarantee of installation facilities and production equipments' were the most difficult as 9 subjects (37.5%), and In the trouble steps in such exposure, the item of 'the synthesis and distribution' steps were 4 times, respectively (30.8%). In the score of the behavior level in radiation safety managements, the minimum and maximum scores were 2.42 and 4.00, respectively, and the average score was $3.46{\pm}0.47$ out of 4. Prosperity and well-being programs in the behavior and job in radiation safety managements (r=0.529) represented a significant correlation statistically. In the drawing of a prediction model based on the factors that affected the behavior in radiation safety managements, general characteristics, organization characteristics, and selfefficacy didn't show a significant path statistically in which the prosperity and well-being programs in job characteristics affected the behavior in radiation safety managements. Therefore, it is necessary to establish a strategy that improves the level of prosperity and well-being levels in job characteristics in order to increase the behavior in radiation safety managements. Thus, this study provides basic materials for the radiation safety management of Cyclotron through the full-scale investigation that is first applied in Korea.

Radiation safety: a focus on lead aprons and thyroid shields in interventional pain management

  • Cheon, Bo Kyung;Kim, Cho Long;Kim, Ka Ram;Kang, Min Hye;Lim, Jeong Ae;Woo, Nam Sik;Rhee, Ka Young;Kim, Hae Kyoung;Kim, Jae Hun
    • The Korean Journal of Pain
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    • v.31 no.4
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    • pp.244-252
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    • 2018
  • C-arm fluoroscopy is useful equipment in interventional pain management because it helps to guide correct needle targeting for the accurate injection and drug delivery. However, due to increased use of C-arm fluoroscopy in various pain procedures, the risk of radiation exposure is a significant concern for pain physicians. The harmful biological effects of ionizing radiation on the human body are well known. It is therefore necessary to strive to reduce radiation exposure. Lead aprons with thyroid shields are the most fundamental radiation protective devices for interventional procedures, and are very effective. However, the operator's radiation safety cannot be guaranteed because pain physicians seem to lack sufficient interest, knowledge, and awareness about radiation safety. Also, inappropriate care and use of radiation protective devices may result in a higher risk of radiation exposure. The purpose of this article was to review the literature on radiation safety with a focus on lead aprons and thyroid shields and present recommendations related to those devices during C-arm fluoroscopic-guided interventions by pain physicians.

Radiation safety management for diagnostic radiation generators and employees in animal hospitals in Korea (동물병원의 진단용 방사선 발생장치 및 방사선종사자 안전관리 실태 조사)

  • An, Hyo-Jin;Kim, Chung-Hyun;Kwon, Young-Jin;Kim, Don-Hwan;Wee, Sung-Hwan;Moon, Jin-San
    • Korean Journal of Veterinary Research
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    • v.54 no.3
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    • pp.151-157
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    • 2014
  • A nationwide survey on radiation safety management in Korean animal hospitals was conducted. By 2013, 53 radiation generators were registered as veterinary medical devices (41 X-ray generators and 12 computed tomography scanners). Additionally there were six approved laboratories for radiation equipment and protection facility, and five approved laboratories for radiation exposure of employees, respectively. By March 2013, 2,030 out of 3,829 animal hospitals operated radiation-generating devices. Among these devices, 389 (19.2%) out of 2,030 were not labeled with the model name and 746 (36.7%) were not labeled with production dates. Thus, most veterinary X-ray generators were outdated (42.6%) and needed replacements. When periodic inspections of 2,018 animal hospitals were performed after revision of the Veterinarians Act in 2011, the hospitals were found to be equipped with appropriate radiation generators and protection facilities. Among 2,545 employees exposed to radiation at the hospitals, 93.9% were veterinarians, 4.3% were animal nurse technicians, and 18% held other positions. Among 169 employees supervised by administrators, none of those had a weekly maximum operating load that exceeded $10mA{\cdot}min$. This study suggests that the radiation safety management system of animal hospitals was general good.

Environment Assessing for Airborne Radioactive Particulate Release-introduction of Methods in IAEA Safety Report Series No.19

  • Meng, Dan;Yang, Liu;Shen, Fu;Yang, Yi;Ma, Yinghao;Ma, Tao;Zhang, Zhilong;Fu, Cuiming
    • Journal of Radiation Protection and Research
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    • v.41 no.4
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    • pp.409-417
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    • 2016
  • Background: Airborne radioactive particulate in many important nuclear facilities (particularly nuclear power plants) will have a strong impact on the relative public dose if they are released into the corresponding environment traversing the stack or vents. The radiation protection researchers have regarded the relative environment assessing and estimation of public doses. And the model of assessing impact of discharges radioactive substance to the environment have been recommended by many international organizations (e.g. IAEA) with the nuclear energy safety and radiation protection. Materials and Methods: This paper introduced the generic models that were suggested by International Atomic Energy Agency (IAEA), for use in assessing the impact of discharges of radioactive substances to the environment (e.g. IAEA Safety Report Series No.19). Results and Discussion: The writers of this paper, based on the recommend methods, assessed the discharge limits in some airborne radioactive substances discharging standards. The reasons that IAEA method are introduced are mainly the following considerations: IAEA is one of international organizations with some authorities in the nuclear energy safety and radiation protection; and, more important, the recommend modes are operational methods rather than the methods having little operations such as that have used by some researchers. Conclusion: It is wish that the introduced methods in this paper can be referenced in draft or revise of the standards related to discharges of radioactive substances to the environment.

Simple Calculation Method as a Supplementary Radiation Safety Assessment for Facility with Radiation Generator

  • Kim, Sang-Tae
    • International Journal of Contents
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    • v.14 no.4
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    • pp.65-69
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    • 2018
  • The objective of this study was to conduct a radiation shielding analysis for the facility equipped with radiation generator. The analysis was carried out in two aspects. First, from the aspect of the effect caused by primary and leakage radiation. Second, effect of scattered radiation was evaluated by applying a simple calculation method based on a scattering rate concept since effect of scattered radiation is significantly important at maze entrance of the radiation facility. The calculated results obtained using the simple method were compared to the results calculated using Geant4 code and the measured values. The results calculated by the suggested method indicate that slight error exists in a radiation shielding analysis done at the maze entrance comparing to other two results, while the results evaluated at the outside of the maze entrance door are relatively consistent with other values.

RADIATION SAFETY ASSESSMENT FOR KN-12 SPENT NUCLEAR FUEL TRANSPORT CASK USING MONTE CARLO SIMULATION

  • Kim, J.K.;Kim, G.H.;Shin, C.H.;Choi, H.S.
    • Journal of Radiation Protection and Research
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    • v.26 no.3
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    • pp.207-214
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    • 2001
  • The KN-12 spent nuclear fuel (SNF) transport cask is designed for transportation of up to 12 assemblies and is in standby status for being licensed in accordance with Korea Atomic Energy Act. To evaluate radiation shielding and criticality safety of the KN-12 cask, each case of study was carried out using MCNP4B Code. MCNP code is verified by performing benchmark calculation for the KSC-4 SNF cask designed in 1989. As a result of radiation safety evaluation for the KN-12 cask, calculated dose rates always satisfied the standards at the cask surface, at 2m from the surface in normal transport condition, and at 1 m from the surface in hypothetical accident condition. Maximum dose rate was always arisen on the side of the cask. For normal transport condition, photons primarily contribute to dose rate between two kinds of released sources, neutrons and photons, from spent nuclear fuel but for hypothetical accident condition, contrary case was resulted. The level of calculated dose rate was 27.8% of the limit at the cask surface, 89.3% at 2 m from the cask surface, and 25.1% at 1 m from the cask surface. For criticality analysis, keff resulting from the criticality analysis considering the condition of optimum partial flooding with fresh water is 0.89708(0.00065. The results confirm the standards recommended by all regulations on radiation safety.

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Statistical Analysis Using Living Radiation Survey Data on Processed Products (가공제품에 대한 생활주변방사선 실태조사 자료를 활용한 통계분석)

  • Choi, Kyoungho;Cho, Jung Keun
    • Journal of radiological science and technology
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    • v.43 no.2
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    • pp.123-128
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    • 2020
  • Radiation Following the 2011 Fukushima nuclear accident in Japan, public interest and anxiety about radiation safety increased, and vague anxiety about commonly exposed living radiation was generated. The Atomic Energy Safety Commission has been conducting a survey of processed products that advertise "negative ions" and "far-infrared" emissions under the Living Radiation Safety Management Act. In this study, in-depth analysis was performed from a statistical point of view using the measurement data presented in the Nuclear Safety Committee's actual survey analysis report as secondary data. As a result, there was a statistically significant difference (p<0.005) between latex and civil affairs products. There were also statistically significant differences (p<0.05) in the results of testing whether there were significant differences in the annual exposure dose between groups after categorizing 71 civil products, including radon beds, into bed, bedding, and living and other categories. The correlation analysis results also confirm that, as is commonly known, the annual doses received from processed products are associated with radon derived from U-238 and Th-232.