• Title/Summary/Keyword: Protection, Radiation

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Performance Evaluation of Radiation Protection Apron's (방사선방어 앞치마 성능 평가)

  • Kang, Jong-gu;Kang, Byung-Sam
    • Journal of radiological science and technology
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    • v.42 no.5
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    • pp.373-377
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    • 2019
  • Radiation exposure is on the rise as the working hours of radiation workers increase. Accordingly, the importance of protection products for decreasing the dose of exposure has risen, and excellent X-ray shielding ability and light weight are required. The purpose of this study is to compare the Pb which use currently and other elements in order to reduce the exposure of workers to the most effective protection products. For experiment, we used the general X-ray equipment and angiography equipment, and obtained the Pb and apron's shielding rate. When the shielding rate of Pb and apron was compared in general X-ray equipment, the shielding rate was 95.1% for Pb 0.5 mm, 96.1% for apron 0.5 mmPb and 95.6% for Bi+W 0.5 mmPb. When compared the shielding rate of each aprons in angiography equipment, 0.5 mmPb apron was the highest as 96.4% and Bi+W 0.25 mmPb apron was the lowest as 90.2% at the 50 cm distance. The shielding rate of 0.5 mmPb apron was the highest as 95.7% and Bi+W 0.25 mmPb apron was the lowest as 85.9% at the 100 cm distance. As a result of evaluating the apron efficiency through this study, 0.5 mmPb apron showed the best shielding rate, but it was the heaviest apron. 0.35 mmPb apron and Bi+W 0.25 mmPb apron weighed light but had low shielding rate. Through the results of this experiment, it is recommended that radiation workers reduce radiation exposure by using more efficient protection products.

Analytic Hierarchy Process for Prioritizing Radiation Safety Measures in Medical Institutions

  • Hyun Suk Kim;Heejeong Jeong;Hyungbin Moon;Sang Hyun Park
    • Journal of Radiation Protection and Research
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    • v.49 no.1
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    • pp.40-49
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    • 2024
  • Background: This study aimed to prioritize policy measures to improve radiation safety management in medical institutions using the analytic hierarchy process. Materials and Methods: It adopted three policy options-engineering, education, and enforcement-to categorize safety management measures, the so-called Harvey's 3Es. Then, the radiation safety management measures obtained from the current system and other studies were organized into action plan categories. Using the derived model, this study surveyed 33 stakeholders of radiation safety management in medical institutions and analyzed the importance of each measure. Results and Discussion: As a result, these stakeholders generally identified enforcement as the most important factor for improving the safety management system. The study also found that radiation safety officers and medical physicists perceived different measures as important, indicating clear differences in opinions among stakeholders, especially in improving quality assurance in radiation therapy. Hence, the process of coordination and consensus is likely to be critical in improving the radiation safety management system. Conclusion: Stakeholders in the medical field consider enforcement as the most critical factor in improving their safety management systems. Specifically, the most crucial among the six specific action plans was the "reinforcement of the organization and workforce for safety management," with a relative importance of 25.7%.

Radiological Dose Assessment Due to the Operation of Nuclear Facilities at KAERI Nuclear Site

  • Han, M.H.;Kim, E.H.;Hwang, W.T;Yeom, J.M.;Han, J.T.;Lee, Y.B.;Han, W.J.
    • Journal of Radiation Protection and Research
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    • v.28 no.3
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    • pp.247-254
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    • 2003
  • To prevent the potential health detriment to the public from radioactive effluents, radiological dose assessments due to the operation of nuclear facilities located at Korea Atomic Energy Research Institute (KAERI) site has been performed semiannually in compliance with the Minister of Science and Technology (MOST)'s Notice in Korea. Radiological dose assessment based on the new recommendation of the International Committee on Radiation Protection (ICRP-60) has been conducted since 1998. In this manuscript, a serial activities at KAERI site to meet the regulatory standards for routine releases of radioactive effluents are introduced and discussed including technical approaches. It is clear that each nuclear facility has been operated in compliance with regulatory standards. Furthermore, it is identified that the radiation induced health effects for residents around the site are neglectable.

Factors Influencing Radiation Protection Behaviors of Endoscopy Nurses during Endoscopic Interventional Radiology (내시경하 중재적 방사선 시술 시 간호사의 방사선 방어행위 영향요인)

  • Yun, Bo Young;Park, Jeong Yun
    • Journal of Korean Clinical Nursing Research
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    • v.26 no.3
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    • pp.305-313
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    • 2020
  • Purpose: The purpose of this study was to identify factors influencing the Radiation Protection(RP) behaviors of endoscopy nurses during endoscopic interventional radiology. Methods: A total of 188 endoscopy nurses working at 30 tertiary or general hospitals participated in this questionnaire-based study. The questionnaire included items on general and job related characteristics, RP knowledge, RP attitude, RP behavior, self-efficacy, and safety climate. Data were collected through online surveys from March 22 to April 10, 2019. Results: Multivariate analysis revealed that RP attitude (β=.65, p<.001), safety climate (β=.12, p=.035), self-efficacy (β=.14, p=.009), and existence of RP protocols (β=.11, p=.038) were significant predictors of better RP behavior. Conclusion: The findings showed that the RP behavior of endoscopy nurses was at high levels and the continuing education for endoscopy nurses and development of a radiation safety management education program were important to improve RP behavior.

Intercomparison of the KAERI Reference Photon and Beta Radiation Measurements (한국원자력연구소 기준 광자 및 베타선장 측정의 국제상호비교)

  • Chang, Si-Yeong;Kim, Bong-Hwan;Kim, Jang-Lyul;McDonald, J.C.;Murphy, M.K.
    • Journal of Radiation Protection and Research
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    • v.21 no.4
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    • pp.255-262
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    • 1996
  • This paper describes the results of intercomparison measurements of KAERI reference photon and beta radiation fields between the KAERI and the PNNL(Pacific Northwest National Laboratory), recently performed at KAERI radiation calibration and dosimetry laboratory on the basis of the ANSI N13.11 criteria for personal dosimeter performance test. Each laboratory used her own radiation detectors or measurement devices traceable to her national primary standard in measuring the exposure rates for photon fields, the absorbed dose rates for beta radiation fields. The agreements in reference radiation measurements between two laboratories were found to be less than ${\pm}2.0%$ for photon fields, ${\pm}1.0%$ for beta radiation fields. Therefore, it could be concluded that KAERI reference radiation fields comply well with the international standard and thus can further serve as a national basis for the researches and developments in radiation protection dosimetry in Korea.

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General Requirements Pertaining to Radiation Protection in Diagnostic X-ray Equipment -KFDA DRS 1-1-3 : 2008 base on IEC 60601-1-3:2008- (진단용 엑스선 장치에 있어서 방사선 방어에 대한 일반 요구사항 -IEC 60601-1-3:2008에 근거한 KFDA DRS 1-1-3:2008-)

  • Kang, Hee-Doo;Dong, Kyung-Rae;Kweon, Dae-Cheol;Choi, Jun-Gu;Jeong, Jae-Ho;Jung, Jae-Eun;Ryu, Young-Hwan
    • Korean Journal of Digital Imaging in Medicine
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    • v.11 no.2
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    • pp.69-77
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    • 2009
  • This study gives an account of the collateral standards in IEC 60601-1-3: 2008 specifying the general requirements for basic safety and essential performance of diagnostic X-ray equipment regarding radiation protection as it pertains to the production of X-rays. The collateral standards establish general requirements for safety regarding ionization radiation in diagnostic radiation systems and describe a verifiable evaluation method of suitable requirements regarding control over the lowest possible dose equivalent for patients, radiologic technologists, and others. The particular standards for each equipment can be determined by the general requirements in the collateral standard and the particular standard is followed in the risk management file. The guidelines for radiation safety of diagnostic radiation systems is written up in ISO 13485, ISO 14971, IEC 60601-1-3(2002)1st edition, medical electric equipment part 1-3, and the general requirements for safety-collateral standards: programmable electrical medical systems. Therefore the diagnostic radiation system protects citizens' health rights with the establishment and revisions of laws and standards for diagnostic radiation systems as a background for the general requirements of radiation safe guards applies, as an international trend, standards regarding the medical radiation safety management. The diagnostic radiation system will also assure competitive power through a conforming evaluation unifying the differing standards, technical specifications, and recognized processes.

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Protective Effects of a Herb, Menthae Herba, against Radiation-induced Oxidative DNA Damage

  • Jo, Sung-Kee;H, Heon-O;Uhee Jung;Kim, Sung-Ho;Byun, Myung-Woo
    • Proceedings of the Korean Society of Postharvest Science and Technology of Agricultural Products Conference
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    • 2003.10a
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    • pp.152-152
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    • 2003
  • As utilization of radiation in medicine, industry and biochemical research increases, the protection against radiation damage has become an important issue. Natural products such as herbal medicines are beginning to receive attention as modifiers on the radiation response. In the present study, the protective effect of a herb, Menthae Herba, against radiation-induced DNA damage was evaluated using alkaline single-cell gel electrophoresis (SCGE; comet assay) in the mouse peripheral blood Iymphocytes and the micronucleus formation test in the Chinese hamster ovary (CHO) cells. The tail moment, which was a marker of DNA damage in the SCGE, and the frequency of micronuclei was decreased in groups treated with Mentae Herba extract before exposure to 200 cGy of gamma-ray. We also confirmed its activities to scavenge DPPH and hydroxyl radicals. These experiments demonstrated that Menthae Herba was effective at reducing the radiation-induced damage of DNA and scavenging free radicals. It is plausible that scavenging of free radicals by Menthae Herba may have played an important role in providing the protection against the radiation-induced damage to the DNA. These results indicated that Menthae Herba might be a useful radioprotector and that radical scavenging appears to be one of the mechanisms of radiation protection.

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Enhancing Gamma-Neutron Shielding Effectiveness of Polyvinylidene Fluoride for Potent Applications in Nuclear Industries: A Study on the Impact of Tungsten Carbide, Trioxide, and Disulfide Using EpiXS, Phy-X/PSD, and MCNP5 Code

  • Ayman Abu Ghazal;Rawand Alakash;Zainab Aljumaili;Ahmed El-Sayed;Hamza Abdel-Rahman
    • Journal of Radiation Protection and Research
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    • v.48 no.4
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    • pp.184-196
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    • 2023
  • Background: Radiation protection is crucial in various fields due to the harmful effects of radiation. Shielding is used to reduce radiation exposure, but gamma radiation poses challenges due to its high energy and penetration capabilities. Materials and Methods: This work investigates the radiation shielding properties of polyvinylidene fluoride (PVDF) samples containing different weight fraction of tungsten carbide (WC), tungsten trioxide (WO3), and tungsten disulfide (WS2). Parameters such as the mass attenuation coefficient (MAC), half-value layer (HVL), mean free path (MFP), effective atomic number (Zeff), and macroscopic effective removal cross-section for fast neutrons (ΣR) were calculated using the Phy-X/PSD software. EpiXS simulations were conducted for MAC validation. Results and Discussion: Increasing the weight fraction of the additives resulted in higher MAC values, indicating improved radiation shielding. PVDF-xWC showed the highest percentage increase in MAC values. MFP results indicated that PVDF-0.20WC has the lowest values, suggesting superior shielding properties compared to PVDF-0.20WO3 and PVDF-0.20WS2. PVDF-0.20WC also exhibited the highest Zeff values, while PVDF-0.20WS2 showed a slightly higher increase in Zeff at energies of 0.662 and 1.333 MeV. PVDF-0.20WC has demonstrated the highest ΣR value, indicating effective shielding against fast neutrons, while PVDF-0.20WS2 had the lowest ΣR value. The Monte Carlo N-Particle Transport version 5 (MCNP5) simulations showed that PVDF-xWC attenuates gamma radiation more than pure PVDF, significantly decreasing the dose equivalent rate. Conclusion: Overall, this research provides insights into the radiation shielding properties of PVDF mixtures, with PVDF-xWC showing the most promising results.

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.

AN EVALUATION OF RADIATION DOSES RESULTING FROM THE MEDICAL USE OF HIGH-ENERGY BETA-RAY SOURCES

  • Park, Jae-Woo;Kim, Hyun-Jo
    • Journal of Radiation Protection and Research
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    • v.26 no.3
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    • pp.149-154
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    • 2001
  • Calculational models to evaluate radiation doses resulting from the medical use of high energy beta-ray sources are presented. The radioactive sources considered are Sr-90/Y-90 used as ophthalmic applicator, Re-188 used for treating restenosis of coronary artery, and Ho-166 used for treating hepatic tumors. Typical therapeutic situations which might induce relatively high radiation doses the medical person involved were considered to compute by using MCNP-4C Monte Carlo code the radiation doses. The calculation results suggest that for all of the cases considered, the evaluated radiation doses are negligible compared to the dose limits. It is also found that the effect of Bremsstrahlung radiations on the total dose is insignificant, and hence the conventional lead gown is also effective in shielding beta-rays.

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