• Title/Summary/Keyword: 방사선피폭선량

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Gross Alpha Analysis of Nasal Smear Samples and Internal Dose Assessment Procedure in Radiation Emergency (방사선비상시 비강스메어 시료의 전알파 분석 및 내부피폭선량평가 절차)

  • Yoon, Seokwon;Ha, Wi-Ho;Kim, Mee-Ryeong;Lee, Seung-Sook
    • Journal of Radiation Protection and Research
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    • v.37 no.4
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    • pp.226-230
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    • 2012
  • The gross alpha analysis of nasal smear samples for the radiation emergency and the additional follow-up steps were established. Cotton swab sticks using in local hospitals for nasal smear in Korea were used for the verification. The measurement results of standard samples spiked with certified reference source were well agreed within ${\pm}20%$ compared with reference values. The clearance ratio of smear samples conducted with wet smear condition showed higher value. To eliminate the quenching effect of liquid scintillation samples, dry of smear samples should be followed up before counting samples. Based on the measurement results, medical decision levels and internal dose assessment were established for the victims in the beginning of radiation emergency.

Assessment of DRL for Computed Tomography in Local Hospital (지역병원에서의 전산화단층촬영 검사에 대한 DRL 평가)

  • Choi, Seok-Yoon
    • Journal of the Korean Society of Radiology
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    • v.16 no.5
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    • pp.619-625
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    • 2022
  • In the field of imaging medicine, computed tomography is one of the most common test methods and one of the most frequently used test methods in hospitals. However, it is accompanied by a very high radiation exposure compared to other test methods. In order to reduce exposure, CT scans should be performed only when absolutely necessary, and even if the tests are performed because they are absolutely necessary, a protocol that serves the purpose of the test and allows the test to be performed in a small dose should be used. In this study, we wanted to learn about the most up-to-date radiation dose usage information used by the region's leading general hospitals and develop a diagnostic reference level (DRL). In the experimental results, the Head CT and Abdomen CT tests showed that DLP was higher than the NRPB (U.K) and Korean DRL. The DLP values used by Chest CT were low for all 3 types of CT devices. The hospital found that efforts to reduce exposure should be made during CT examinations, and in particular, Head CT and Abdomen CT determined that efforts to reduce exposure were necessary.

Assessment of Inhalation Dose Sensitivity by Physicochemical Properties of Airborne Particulates Containing Naturally Occurring Radioactive Materials (천연방사성물질을 함유한 공기 중 부유입자 흡입 시 입자의 물리화학적 특성에 따른 호흡방사선량 민감도 평가)

  • Kim, Si Young;Choi, Cheol Kyu;Park, Il;Kim, Yong Geon;Choi, Won Chul;Kim, Kwang Pyo
    • Journal of Radiation Protection and Research
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    • v.40 no.4
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    • pp.216-222
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    • 2015
  • Facilities processing raw materials containing naturally occurring radioactive materials (NORM) may give rise to enhanced radiation dose to workers due to chronic inhalation of airborne particulates. Internal radiation dose due to particulate inhalation varies depending on particulate properties, including size, shape, density, and absorption type. The objective of the present study was to assess inhalation dose sensitivity to physicochemical properties of airborne particulates. Committed effective doses to workers resulting from inhalation of airborne particulates were calculated based on International Commission on Radiological Protection 66 human respiratory tract model. Inhalation dose generally increased with decreasing particulate size. Committed effective doses due to inhalation of $0.01{\mu}m$ sized particulates were higher than doses due to $100{\mu}m$ sized particulates by factors of about 100 and 50 for $^{238}U$ and $^{230}Th$, respectively. Inhalation dose increased with decreasing shape factor. Shape factors of 1 and 2 resulted in dose difference by about 18 %. Inhalation dose increased with particulate mass density. Particulate mass densities of $11g{\cdot}cm^{-3}$ and $0.7g{\cdot}cm^{-3}$ resulted in dose difference by about 60 %. For $^{238}U$, inhalation doses were higher for absorption type of S, M, and F in that sequence. Committed effective dose for absorption type S of $^{238}U$ was about 9 times higher than dose for absorption F. For $^{230}Th$, inhalation doses were higher for absorption type of F, M, and S in that sequence. Committed effective dose for absorption type F of $^{230}Th$ was about 16 times higher than dose for absorption S. Consequently, use of default values for particulate properties without consideration of site specific physiochemical properties may potentially skew radiation dose estimates to unrealistic values up to 1-2 orders of magnitude. For this reason, it is highly recommended to consider site specific working materials and conditions and use the site specific particulate properties to accurately access radiation dose to workers at NORM processing facilities.

Suggestion of The Manual Exposure Condition Guideline for Reducing Patient Dose in Digital Breast Tomosynthesis (디지털 유방단층촬영의 피폭선량 경감을 위한 수동 촬영조건의 가이드라인 제시)

  • Hong, Eun-Ae;Lee, In-Ja
    • Journal of radiological science and technology
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    • v.39 no.4
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    • pp.483-491
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    • 2016
  • The conditions after exposure to digital mammography and digital breast tomosynthesis were analyzed. The examinations for the ACR phantom were done using manual exposure, not auto exposure, to examine image discrimination and patient dose. As a result, the following results were derived: In the CC exposure, the kVp was 2kVp higher while mAs decreased to 58.6% for the 3D tomography. Such result showed an approximate decrease of 60mAs. At that time, the patients' Average Glandular Dose (AGD) was 1.65mGy in 2D and 1.87mGy in 3D; thus, AGD of 3D was shown to have about 1.13times higher. The result of the manual exposure revealed a reduced mAs of up to 80%; there was no effect in the assessment standard in terms of image discrimination, resulting in more than 10 points. When mAs was reduced to 80% in the manual exposure for ACR phantom, AGD was decreased to 0.66mGy. The diagnostic values of images were maintained and patients dose was reduced in the manual exposure in the AEC condition for 3D. Since the use of 3D has recently increased, using the manual exposure has been recommended in this study to improve the diagnostic value, while, simultaneously reducing patients dose.

A Study to Decrease Exposure Dose for the Radiotechnologist in PET/CT (PET/CT 검사에서 방사선 종사자 피폭선량 저감에 대한 방안 연구)

  • Cho, Seok-Won;Park, Hoon-Hee;Kim, Jung-Yul;Ban, Yung-Kak;Lim, Han-Sang;Oh, Ki-Beak;Kim, Jae-Sam;Lee, Chang-Ho
    • The Korean Journal of Nuclear Medicine Technology
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    • v.14 no.2
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    • pp.159-165
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    • 2010
  • Purpose: Positron emission tomography scan has been growing diagnostic equipment in the development of medical imaging system. Compare to $^{99m}Tc$ emitting 140 keV, Positron emission radionuclide emits 511 keV gamma rays. Because of this high energy, it needs to reduce radioactive emitting from patients for radiotechnologist. We searched the external dose rates by changing distance from patients and measure the external dose rates when we used shielder investigate change external dose rates. In this study, the external dose distribution were analyzed in order to help managing radiation protection of radiotechnologists. Materials and Methods: Ten patients were searched (mean age: $47.7{\pm}6.6$, mean height: $165.5{\pm}3.8$ cm and mean weight: $65.9{\pm}1.4$ kg). Radiation were measured on the location of head, chest, abdomen, knees and toes at the distance of 10, 50, 100, 150 and 200 cm. Then, all the procedure was given with a portable radiation shielding on the location of head, chest and abdomen at the distance of 100, 150 and 200 cm and transmittance was calculated. Results: In 10 cm, head (105.40 ${\mu}Sv/h$) was the highest and foot (15.85 ${\mu}Sv/h$) was the lowest. In 200 cm, head, chest and abdomen showed similar. On head, the measured dose rates were 9.56 ${\mu}Sv/h$, 5.23 ${\mu}Sv/h$, and 3.40 ${\mu}Sv/h$ in 100, 150 and 200 cm respectively. When using shielder, it shows 2.24 ${\mu}Sv/h$, 1.67 ${\mu}Sv/h$, and 1.27 ${\mu}Sv/h$ in 100, 150 and 200 cm on head. On chest, the measured dose rates were 8.54 ${\mu}Sv/h$, 4.90 ${\mu}Sv/h$, 3.44 ${\mu}Sv/h$ in 100, 150 and 200 cm, respectively. When using shielder, it shows 2.27 ${\mu}Sv/h$, 1.34 ${\mu}Sv/h$, and 1.13 ${\mu}Sv/h$ in 100, 150 and 200 cm on chest. On abdomen, the measured dose rates were 9.83 ${\mu}Sv/h$, 5.15 ${\mu}Sv/h$ and 3.18 ${\mu}Sv/h$ in 100, 150 and 200cm respectively. When using shielder, it shows 2.60 ${\mu}Sv/h$, 1.75 ${\mu}Sv/h$ and 1.23 ${\mu}Sv/h$ in 100, 150 and 200 cm on abdomen. Transmittance was increased as the distance was expanded. Conclusion: As the distance was further, the radiation dose were reduced. When using shielder, the dose were reduced as one-forth of without shielder. The Radio technologists are exposed of radioactivity and there were limitations on reducing the distance with Therefore, the proper shielding will be able to decrease radiation dose to the radiotechnologists.

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Reference levels for patient Radiation Dose in interventional radiological procedures (중재적 방사선 시술 시 환자선량에 대한 참고 준위 비교)

  • Park, Hyeok;Kim, Yong-Wan;Jeon, Ju-Seob
    • Journal of the Korean Society of Radiology
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    • v.6 no.1
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    • pp.11-17
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    • 2012
  • The purpose of this study is to measure and evaluate radiation dose on patients in interventional radiological(IVR) procedures classified by each procedure, and aid as data for safety management. Fluroscopy time(F-time), dose area product(DAP) and number of acquired images from each kind of procedure was checked. Non-vascular procedures showed low value, and vascular procedure showed high value in all procedures except in IVC filter. F-time was longest in EVAR, which showed also the highest DAP value of all procedures. DAP-rate showed high value in TACE. By this result, we attempt to establish standard guideline of radiation dose on patients in IVR procedure.

구내 방사선 촬영에 있어서 Film과 Digital sensor에 따른 피폭선량의 차이에 대한 비교

  • Kim, Ju-Yeong
    • Korean Journal of Digital Imaging in Medicine
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    • v.7 no.1
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    • pp.45-49
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    • 2005
  • 목적 : 기존 구내 방사선 촬영에서 사용되었던 Film에서의 노출선량과 Digital Sensor를 이용한 구내 디지털 촬영에서의 노출선량을 비교하여 현재 광범위 하게 사용 되어지고 있는 Digital Sensor가 환자의 피폭선량을 감소하는데 기여하는 정도를 알아본다. 대상 및 방법 : 치아 우식증이 없는 5개의 구치부 치아를 선택하여 석고 블럭에 매식한 후 교합면과 인접면에 우식병소들을 형성하였다. 이를 필름(Kodak Insight; IS, Kodak Co, USA)과 Digital Sensor(Kodak RVG 6000; Kodak Co, USA)에 XCP Instrument(Rinn Co, USA)를 사용하고, 전면에는 조직등가물질인 Acrylic Resin Block 20mm를 설치하였다. Acrylic Resin Block의 관구 측면 에서는 조사선량계를 부착하여 단계별로 변화시키는 노출조건에 대한 조사선량을 측정하였다. 그리고 이렇게 얻어진 영상을 3명의 방사선학 전공의와 1명 의 보존과 전공의가 평가를 하였다. 결과 : Film과 Digital Sensor를 가지고 촬영한 영상을 분석한 결과 노출선량에서도 Digital Sensor는 Film 노출선량과 비슷한 결과를 도출해 낼 수 있었다. 그러나 Digital Sensor로 촬영된 영상의 경우에는 Film 경우보다 좀더 효과적으로 조사선량을 판단 할 수 있었으며, 또한 영상 판독시 필름보다 폭 넓게 응용 할 수 있었다. 결론 : 본 연구에서는 선량 변화에만 의존하는 것이 아니라 Digital Sensor로 촬영시 영상 조절을 병행한다면 좀더 정확하고 효과적인 진단 활동에 도움이 될 수 있을 것으로 사료된다.

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Characterization of Radiation Field in the Steam Generator Water Chambers and Effective Doses to the Workers (증기발생기 수실의 방사선장 특성 및 작업자 유효선량의 평가)

  • Lee, Choon-Sik;Lee, Jai-Ki
    • Journal of Radiation Protection and Research
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    • v.24 no.4
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    • pp.215-223
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    • 1999
  • Characteristics of radiation field in the steam generator(S/G) water chamber of a PWR were investigated and the anticipated effective dose rates to the worker in the S/G chamber were evaluated by Monte Carlo simulation. The results of crud analysis in the S/G of the Kori nuclear power plant unit 1 were adopted for the source term. The MCNP4A code was used with the MIRD type anthropomorphic sex-specific mathematical phantoms for the calculation of effective doses. The radiation field intensity is dominated by downward rays, from the U-tube region, having approximate cosine distribution with respect to the polar angle. The effective dose rates to adults of nominal body size and of small body size(The phantom for a 15 year-old person was applied for this purpose) appeared to be 36.22 and 37.06 $mSvh^{-1}$) respectively, which implies that the body size effect is negligible. Meanwhile, the equivalent dose rates at three representative positions corresponding to head, chest and lower abdomen of the phantom, calculated using the estimated exposure rates, the energy spectrum and the conversion coefficients given in ICRU47, were 118, 71 and 57 $mSvh^{-1}$, respectively. This implies that the deep dose equivalent or the effective dose obtained from the personal dosimeter reading would be the over-estimate the effective dose by about two times. This justifies, with possible under- or over- response of the dosimeters to radiation of slant incidence, necessity of very careful planning and interpretation for the dosimetry of workers exposed to a non-regular radiation field of high intensity.

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Consideration about Radiological Technology Student's Frequent Workers Exposure Dose Rate (방사선과 재학생의 수시출입자 방사선 피폭선량에 대한 고찰)

  • Park, Hoon-Hee
    • Journal of radiological science and technology
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    • v.41 no.6
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    • pp.573-580
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    • 2018
  • The Nuclear Safety Commission amended the Nuclear Safety Act by strengthening the safety management system for the frequent workers to the level of radiation workers. And students entering radiation management zones for testing and practical purposes are subject to frequent workers. It is inevitable that this will incur additional costs. In this paper, the validity of the amendment to the Nuclear Safety Act was to be assessed in terms of radiation protection. Study subjects are from 2014 to 2016, among university students in Seong-nam Korea and comparisons for analyses were made taking into account variables that are differences in annual, practical types, on-class and clinical practice students exposure dose. The analysis showed that exposures between on-class and clinical practice received were less than the annual dose limit of 1 mSv for the public. Then, some alternatives that excluding from frequent workers during on-class practice or mitigating the frequent workers' safety regulation for only on-class frequent workers can be considered. Optimization is how rational is the reduction in exposure dose to the costs required. Therefore, the results are hardly considered for optimization. If the data accumulated, it could be considered that the revision of the act could be evaluated and improved.