• 제목/요약/키워드: Radiation exposure dose

검색결과 1,108건 처리시간 0.023초

심장내과의 중재적 시술시 시술조건에 따른 방사선사의 방사선 노출 특성 (The Characteristic of Radiation Exposure for Radiologist with Applying Condition in Interventional Radiology in Cardiology)

  • 박정규;조의현
    • 디지털콘텐츠학회 논문지
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    • 제13권3호
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    • pp.421-429
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    • 2012
  • 최근 방사선 의료에서 중재적 시술의 확대로 인하여 시술 건수가 증가하고 있으며, 시술자에 따라 방사선 노출이 다르게 나타 날 수 있으며 시술자와 환자가 받는 방사선 피폭의 증가를 가져온다. 본 연구는 2011년 11월 01일부터 2012년 01월 31일 까지 경북지역 S대학 병원에 내원한 303명의 심장내과 환자를 대상으로 중재적 방사선시술을 시행한 시술자 5명에 따른 방사선 노출특성을 비교분석하였다. 투시시간의 경우 5명의 시술의의 평균 투시시간은 697.95초, cumulative DAP(exp)의 경우 평균 환자 면적선량은 $52,730mGycm^2$, total DAP의 경우 평균 환자면적선량은 $104,875.14mGycm^2$, acquired image의 경우 평균 영상은 855.52frame, exposure image의 평균 영상은 802.2frame로 나타나 통계적으로 유의한 차이를 보였다(p<0.05). 장비의 X선 노출 특성 즉, 투시시간, cumulative DAP(fluro), cumulative DAP(exp), total DAP, acquired image, exposure image는 서로 높은 상관관계를 보이나 cumulative DAP(exp)와 acquired runs는 상관관계를 보이지 않았다. 시술자와 가장 큰 비중을 차지하는 것은 투시시간으로 나타나 투시시간이 길어질수록 방사선 피폭이 증가함을 의미한다. 시술시 피폭선량은 시술자에 따라 시술능력과 경험, 시술의 난이도 및 정밀 시술여부와 관련 있으며, 혈관 조영의 횟수와 투시시간이 정해진 것이 아니어서 인위적인 조절이 어려운 부분이라 할 수 있다. 따라서, 중재방사선 절차를 수행하는 의료진의 실질 피폭을 합리적으로 평가하는 시스템이 필요하며, 불필요한 피폭을 줄이기 위해 시술자를 비롯한 방사선 작업종사자에 대한 자체교육과 훈련이 필요할 것으로 사료된다.

Analysis of Trends in Dose through Evaluation of Spatial Dose Rate and Surface Contamination in Radiation-Controlled Area and Personal Exposed Dose of Radiation Worker at the Korea Institute of Radiological and Medical Sciences (KIRAMS)

  • Lee, Bu Hyung;Kim, Sung Ho;Kwon, Soo Il;Kim, Jae Seok;Kim, Gi-sub;Park, Min Seok;Park, Seungwoo;Jung, Haijo
    • 한국의학물리학회지:의학물리
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    • 제27권3호
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    • pp.146-155
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    • 2016
  • As the probability of exposure to radiation increases due to an increase in the use of radioisotopes and radiation generators, the importance of a radiation safety management field is being highlighted. We intend to help radiation workers with exposure management by identifying the degree of radiation exposure and contamination to determine an efficient method of radiation safety management. The personal exposure doses of the radiation workers at the Korea Institute of Radiological & Medical Sciences measured every quarter during a five-year period from Jan. 1, 2011 till Dec. 31, 2015 were analyzed using a TLD (thermoluminescence dosimeter). The spatial dose rates of radiation-controlled areas were measured using a portable radioscope, and the level of surface contamination was measured at weekly intervals using a piece of smear paper and a low background alpha/beta counter. Though the averages of the depth doses and the surface doses in 2012 increased from those in 2011 by about 14%, the averages were shown to have decreased every year after that. The exposure dose of 27 mSv in 2012 increased from that in 2011 in radiopharmaceutical laboratories and, in the case of the spatial dose rate, the rate of decrease in 2012 was shown to be similar to the annual trend of the whole institute. In the case of the surface contamination level, as the remaining radiation-controlled area with the exception of the I-131 treatment ward showed a low value less than $1.0kBq/m^2$, the annual trend of the I-131 treatment ward was shown to be similar to that of the entire institute. In conclusion, continuous attention should be paid to dose monitoring of the radiation-controlled areas where unsealed sources are handled and the workers therein.

Radiation exposure dose in human blood lymphocytes as assessed by the CBMN assay

  • Ryu, Tae Ho;Kim, Jin-Hong;Kim, Jin Kyu
    • Journal of Ecology and Environment
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    • 제37권4호
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    • pp.195-200
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    • 2014
  • The chances of accidental exposure are augmented as the application of ionizing radiation increases in various fields. Such accidental exposures may occur at nuclear power plants, laboratories, and hospitals. Cytogenetic assays have been used for estimating radiation dose in the situation of the accidents. The micronucleus assay has several advantages over the other cytogenetic methods as it is simple and fast. The present study aimed at investigation of the micronuclei frequencies in cytokinesis-block cells in human blood lymphocytes after ${\gamma}$-irradiation and at establishment of a standard dose response relationship. The samples of peripheral blood were obtained from 6 different donors aged between 24 and 30 years old. The bloods were irradiated in vitro with 0-5 Gy. A linear quadratic dose-response equation was obtained by scoring the micronuclei in binucleated cells; $y=27.87x^2+46.13x+2.08$ ($r^2=0.99$). Irradiation caused a significant decrease in the nuclear division index. Necrotic and apoptotic cells increased in number after irradiation in a dose-dependent manner. In conclusion, the conventional cytokinesis-block micronucleus assay has proven to be the great technique in biological dosimetry. Dose-response calibration curve derived from CMBN assay could be used to estimate the exposure dose during a radiological emergency.

원자력안전법에 대한 방사선학과 학생들의 학습권 보장에 관한 연구 (A Study on the Guarantee of Learning Rights of Radiology Students in Nuclear Safety Act)

  • 이보우
    • 대한방사선기술학회지:방사선기술과학
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    • 제45권2호
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    • pp.159-164
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    • 2022
  • The study developed a radiation dose measurement program in the radiology laboratory to measure how much exposure the students are exposed to during the radiology class, to request for the improvement and the revision of the current Nuclear Safety Act. The experimental program is shown in the following figure, and experiments were conducted to determine the degree of radiation exposure in the control room with a lead gown at a distance of 1 m, 2 m, and 1 m, and in a control room with a radiographic lead glass wall. The duration of the experiment was 3 months from April to June, when radiation imaging practice classes were conducted, and 128 hours of imaging practice per month were conducted. In order to find out the dose of radiation dose during radiology imaging practice class, the experiment was carried out from April to June for 3 months, and according to the program, the results of exposure dose were 0.34 mSv at 1 m distance, 0.01 mSv at shielding of lead gown at 1 m distance, 0.16 mSv at 2 m distance, and 0.01 mSv at control room with radiation lead glass wall. The exposure dose from the test results was much below the annual general public limit dose of 1 mSv. The restriction on the operation of the radiation equipment in the practice of the students is a regulation that infringes the right of students to learn, and amendments or exemptions of Nuclear Safety Act should be enacted to ensure that it does not violate the fundamental right to learn for students in radiology.

제조사별 다중 검출기 컴퓨터단층촬영 장비의 관전류 자동노출조절 기법의 방사선량 감소 평가 (Evaluation of Radiation Dose Reduction from the Automatic Exposure Control Technique in Different Manufactures Multi-Detector Computed Tomography)

  • 김영옥;성열훈
    • 대한안전경영과학회:학술대회논문집
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    • 대한안전경영과학회 2011년도 추계학술대회
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    • pp.563-571
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    • 2011
  • The purpose of the study was to evaluation of the radiation dose reduction using various automatic exposure control (AEC) systems in different manufactures multi-detector computed tomography (MDCT). We used three different manufacturers for the study: General Electric Healthcare, Philips Medical systems and Siemens Medical Solutions. The general scanning protocol was created for the each examination with the same scanning parameters as many as possible. In the various AEC systems, the evaluation of reduced-dose was evaluated by comparing to fixed mAs with using body phantom. Finally, when we applied to AEC for three manufacturers, the radiation dose reduction decreased each 35.3% in the GE, 58.2% in the Philips, and 48.6% in the Siemens. This applies to variety of the AEC systems which will be very useful to reduce the dose and to maintain the high quality.

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방사선 개인피폭선량계를 이용한 피폭선량 측정 및 유용성 평가 (Evaluation of Usability and Radiation Dose Measurement Using Personal Radiation Exposure Dosimeter)

  • 강인석;안성민
    • 한국콘텐츠학회논문지
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    • 제14권11호
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    • pp.864-870
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    • 2014
  • 선량계 유용성을 평가하기 위한 방법으로 방사선관계종사자의 피폭선량을 측정하여 개인피폭관리를 위한 선량계 선택의 기초 자료를 제시하고자 하였다. 2012년 1년간 방사선사 30명을 대상으로 하였으며 개인피폭 누적선량을 측정하여 열형광선량계, 형광유리선량계, 광자극발광선량계의 성능을 조사하였다. 연구방법으로는 DAP와 ion-chamber를 이용하여 세종류 개인피폭선량계의 선량측정값을 비교 분석하였으며 의료기관별, 검사업무별, 분기별 방사선관계종사자의 피폭누적선량을 확인하였다. 결과적으로 직접 X선조사를 통한 개인피폭선량계의 선량값과 ion-chamber의 절대값에서 광자극발광선량계가 열형광선량계나 형광유리선량계에 비해 더 유사한 선량값을 나타내 측정 능력면에서 더 우수한 결과를 나타냈다. 또한 방사선발생구역에서 방사선관계종사자의 피폭선량이 광자극발광선량계에서 보다 높게 나타났다.

극저준위 콘크리트, 금속 해체방폐물의 방사선적 특성을 고려한 매립형 처분시설 방사선작업자 예비 피폭선량 평가 (Preliminary Radiation Exposure Dose Evaluation for Workers of the Landfill Disposal Facility Considering the Radiological Characteristics of Very Low Level Concrete and Metal Decommissioning Wastes)

  • 도호석;조예슬;강현구;하재철
    • 방사선산업학회지
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    • 제17권4호
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    • pp.509-518
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    • 2023
  • The Kori Unit 1 nuclear power plant, which is planned to be dismantled after permanent shutdown, is expected to generate a large amount of various types of radioactive waste during the dismantling process. For the disposal of Very-low-level waste, which is expected to account for the largest amount of generation, the Korea Radioactive waste Agency (KORAD) is in the process of detailed design to build a 3-phase landfill disposal facility in Gyeongju. In addition, a large container is being developed to efficiently dispose of metal and concrete waste, which are mainly generated as Very low-level waste of decommissioning. In this study, based on the design characteristics of the 3-phase landfill disposal facility and the large container under development, radiation exposure dose evaluation was performed considering the normal and accident scenarios of radiation workers during operation. The direct exposure dose evaluation of workers during normal operation was performed using the MCNP computer program, and the internal and external exposure dose evaluation due to damage to the decommissioning waste package during a drop accident was performed based on the evaluation method of ICRP. For the assumed scenario, the exposure dose of worker was calculated to determine whether the exposure dose standards in the domestic nuclear safety act were satisfied. As a result of the evaluation, it was confirmed that the result was quite low, and the result that satisfied the standard limit was confirmed, and the radiational disposal suitability for the 3-phase landfill disposal facility of the large container for dismantled radioactive waste, which is currently under development, was confirmed.

The System of Radiation Dose Assessment and Dose Conversion Coefficients in the ICRP and FGR

  • Kim, Sora;Min, Byung-Il;Park, Kihyun;Yang, Byung-Mo;Suh, Kyung-Suk
    • Journal of Radiation Protection and Research
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    • 제41권4호
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    • pp.424-435
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    • 2016
  • Background: The International Commission on Radiological Protection (ICRP) recommendations and the Federal Guidance Report (FGR) published by the U.S. Environmental Protection Agency (EPA) have been widely applied worldwide in the fields of radiation protection and dose assessment. The dose conversion coefficients of the ICRP and FGR are widely used for assessing exposure doses. However, before the coefficients are used, the user must thoroughly understand the derivation process of the coefficients to ensure that they are used appropriately in the evaluation. Materials and Methods: The ICRP provides recommendations to regulatory and advisory agencies, mainly in the form of guidance on the fundamental principles on which appropriate radiological protection can be based. The FGR provides federal and state agencies with technical information to assist their implementation of radiation protection programs for the U.S. population. The system of radiation dose assessment and dose conversion coefficients in the ICRP and FGR is reviewed in this study. Results and Discussion: A thorough understanding of their background is essential for the proper use of dose conversion coefficients. The FGR dose assessment system was strongly influenced by the ICRP and the U.S. National Council on Radiation Protection and Measurements (NCRP), and is hence consistent with those recommendations. Moreover, the ICRP and FGR both used the scientific data reported by Biological Effects of Ionizing Radiation (BEIR) and United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) as their primary source of information. The difference between the ICRP and FGR lies in the fact that the ICRP utilized information regarding a population of diverse races, whereas the FGR utilized data on the American population, as its goal was to provide guidelines for radiological protection in the US. Conclusion: The contents of this study are expected to be utilized as basic research material in the areas of radiation protection and dose assessment.

Exposure of the Population in the United States to Ionizing Radiation

  • Carter Melvin W.;Oliver Robert W.
    • Journal of Radiation Protection and Research
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    • 제12권2호
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    • pp.37-50
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    • 1987
  • The exposure of the population in the United States to ionizing radiation has recently been evaluated by the National Council on Radiation Protection and Measurements (NCRP). This was done by constituting six organizational groups to address various phases of the work and the results of this work are summarized in this article. The article is based on the report, by the same title, which is scheduled for publication by the NCRP in September, 1987. The six organizational groups are titled Radiation Exposure from Consumer Products, Natural Background Radiation, Radiation Associated with Medical Examinations, Radiation Received by Radiation Employees, Public Exposure from Nuclear Power, and Exposure from Miscellaneous Environmental Sources. These titles are descriptive of the subject areas covered by each of these separate groups. The data evaluated are for the years 1977-1984 with the majority of the data being for the period 1980-1982. Summary information is presented and discussed for the number of people exposed to given sources, the effective dose equivalent, the average effective dose equivalent to the U.S. population, and the genetically significant dose equivalent. The average annual effective dose equivalent from all sources to the U.S. population is approximately 3.6 mSv (360 mrem). Exposures to natural sources make the largest contribution to this total. Radon and radon decay products contribute 2.0 mSv (200 mrem) whereas the other naturally occurring radionuclides contribute 1.0 mSv (100 mrem). Among man-made or enhanced sources, medical exposures make the largest additional contributions, namely 0.39 mSv (39 mrem) for diagnosis and 0.14 mSv (14 mrem) for nuclear medicine. It was not possible to evaluate exposures for therapy. Most of the other sources of population exposure, including nuclear power and consumer products, are minor. A possible exception would be the use of tobacco products. These exposures are discussed in relation to a negligible individual risk level of $10{\mu}Sv/y$ (1 mrem/y). The NCRP considers exposures below the negligible individual risk level as trivial and as such should be dismissed.

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Evaluation of exposure to ionizing radiation of medical staff performing procedures with glucose labeled with radioactive fluorine - 18F-FDG

  • Michal Biegala;Marcin Brodecki;Teresa Jakubowska;Joanna Domienik-Andrzejewska
    • Nuclear Engineering and Technology
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    • 제56권1호
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    • pp.335-339
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    • 2024
  • Employees of nuclear medicine facilities performing medical procedures with the use of open radioactive sources require continuous detailed control of exposure to ionizing radiation. Thermoluminescent (TL) detectors placed in dosimeters: for the whole body, for lenses, ring and wrist dosimeters were used to assess exposure. The highest whole-body exposure of (1.70 ± 1.09) µSv/GBq was recorded in nurses administering radiopharmaceutical to patients. The highest exposure to lenses and fingers was recorded for employees of the quality control zone and it was (8.08 ± 2.84) µSv/GBq and a maximum of (1261.46 ± 338.93) µSv/GBq, respectively. Workers in the production zone received the highest doses on their hands, i.e. (175.67 ± 13.25) µSv/GBq. The measurements performed showed that the analyzed workers may be classified as exposure category A. Wrist dosimeters are not recommended for use in isotope laboratories due to underestimation of ionizing radiation doses. Appropriately selected shields, which significantly reduce the dose received by employees, must be used in isotope laboratories. Periodic measurements confirmed that the appropriate optimization of exposure reduces the radiation doses received by employees.