• Title, Summary, Keyword: 내부피폭

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The Whole Body Counting Experience on the Internal Contamination of $^{131}I$ at Korean Nuclear Power Plants (전신계측기를 이용한 원전종사자의 $^{131}I$ 내부방사능 측정 경험 및 개선방향에 대한 연구)

  • Kim, Hee-Geun;Kong, Tae-Young
    • Journal of Radiation Protection and Research
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    • v.34 no.3
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    • pp.121-128
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    • 2009
  • During the maintenance period at Korean nuclear power plants, internal exposure of radiation workers occurred by the inhalation of $^{131}I$ released to the reactor building when primary system was opened. The internal radioactivity of radiation workers contaminated by $^{131}I$ was immediately measured using a whole body counter and the whole body counting was performed again after a few days. In this study, the intake estimated from the record history of entrance to radiation control areas and the measurement results of air sampling for $^{131}I$ in those areas, were compared with that from the results of whole body counting. As a result, it was concluded that the intake estimation using whole body counting and air sampling showed similar results.

An Effects of Radiation Dose Assessment for Radiation Workers and the Member of Public from Main Radionuclides at Nuclear Power Plants (원전에서 발생하는 주요 방사성핵종들이 방사선작업종사자와 원전 주변주민의 피폭방사선량 평가에 미치는 영향)

  • Kim, Hee-Geun;Kong, Tae-Young;Jeong, Woo-Tae;Kim, Seok-Tae
    • Journal of Radiation Protection and Research
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    • v.35 no.1
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    • pp.12-20
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    • 2010
  • In a primary system at nuclear power plants (NPPs), various radionuclides including fission products and corrosion products are generated due to the complex water conditions. Particularly, $^3H,\;^{14}C,\;^{58}Co,\;^{60}Co,\;^{137}Cs,\;and^{131}I$ are important radionuclides in respect of dose assessment for radiation workers and management of radioactive effluents. In this paper, the dominant contributors of radiation exposure for radiation workers and the member of public adjacent to NPPs were reviewed and the process of dose assessment attributable to those contributors were introduced. Furthermore, the analysis for some examples of radiation exposure to radiation workers and the public during the NPP operation was carried out. This analysis included the notable precedents of internal radiation exposure and contamination of demineralized water occurred in Korean NPPs. Particularly, the potential issue about the dose assessment of tritium and carbon-14 was also reviewed in this paper.

Ringhals 가압경수로, 고pH치 이점 입증

  • 한국원자력산업회의
    • Nuclear industry
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    • v.7 no.12
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    • pp.31-35
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    • 1987
  • 최근 Ringhals 2호기는 baffle Jetting에 의한 연료손상과 연료내부의 코발트에 의해 문제를 겪었으나, 운전경험으로 고 수소이온농도 (고 리튬농도)의 효과가 입증되었다. 현재 3기의 Ringhals경수로에서는 고 수소이온농도방법이 채택되어, 종사원 피폭의 주 원인인 방사화 부식생성물의 축적을 제어할 수 있음을 보여주고 있다. 다음은 Nuclear Engineering International지 '87년 10월호에 게재된 내용을 번역한 것이다.

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Comparative Analyses of the Internal Radiation Exposures due to Food Chain Pathway Using FOOD III Code (FOOD III 코드를 이용한 섭식경로 내부피폭 비교해석)

  • Choi, Yong-Ho;Chung, Kyu-Hoi;Kim, Jin-Kyu;Lee, Jeong-Ho
    • Journal of Radiation Protection and Research
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    • v.13 no.2
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    • pp.41-51
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    • 1988
  • In order to develop a food-chain computer code suitable to the environmental conditions of Korea, the FOOD III code was partially modified. The excution results for Korean male-adult were compared to those from the Canadian version of FOOD III to deduce a more realistic approach in dose assessment. The amounts of Mn-54, Co-58, Co-60, I-131 and I-132 released from Kori unit 1 in1984 were used as the source terms for the sample calculation. The maximum atmospheric dispersion factor(X/Q) value on the site boundary was applied. Through the code modification, organ doses decreased by about $20{\sim}70%$ and the effective committed dose equivalent by about 40% to be $7.935{\times}10^{-6}Sv/y$ which is 0.16% of the ICRP limit, $5{\times}10^{-3}Sv/y$.

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Indoor Radon Levels and Effective Dose Estimation in Learning and Common Living Space of University (대학 내 학습공간과 공동 생활공간에 대한 실내 라돈 농도 측정과 유효선량 산출)

  • Kim, Jung-Su
    • Journal of the Korean Society of Radiology
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    • v.12 no.3
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    • pp.329-334
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    • 2018
  • Radon which is natural component of air is a colorless and odorless radioactive gas. Radon exposure can also occur from some building materials if they are made from radon-containing substances by breathing. In this study, The radiation dose of radon concentration was detected at 8 buildings of the A university during 3-month from June. 2017 to August. 2017. We detected indoor radon exposure at 8 building of the university and estimated annual effective dose. The radon concentration of Hall G and Hall F of the A university represented 81 and $14Bq/m^3$ respectively and average indoor radon concentration represented $41.63Bq/m^3$. Average effective dose was estimated 0.40 mSv/y, maximum effective dose was 0.78 mSv/y and minimum effective dose was 0.13 mSv/y respectively. University is the place that students spend the almost whole time. We suggest ventilation and appropriate management of a building, which could reduce the natural radiation exposure by radon concentration.

A Study on a position detection of radiation using CCD camera (영상센서를 이용한 방사선원 위치탐지 연구)

  • Lee, Nam-Ho;Choi, Chang-Whan;Shin, Ho-Chul;Jun, Seung-Ho
    • Proceedings of the KIEE Conference
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    • pp.324-326
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    • 2006
  • CCD형 영상소자는 방사선 피폭 시 표면과 격자내부에 모두 손상을 받게 되며, 감마방사선이나 X선과 같은 고에너지의 이온화 방사선에 노출될 경우 격자 실리콘 내부에 전자-전공쌍(Electron-hole pair, EHP)이 발생된다. 이러한 EHP는 CCD의 순간 출력 광전류로 변환되어 백색 화소 형태의 영상잡음으로 가시화되며, 이 화소 수는 피폭 방사선량에 비례하여 증가하는 특성을 지니고 있다. 따라서 출력 영상정보를 분석하면 조사된 방사선의 양과 특성을 측정할 수 있다. 본 연구에서는 CCD를 이용하여 가상의 방사능 물질 누출 공간에서 방사선원의 방향과 거리정보를 고속으로 탐지하기 위한 장치와 고속 측정 알고리즘을 구현하고 실제 방사선장에서 실증시험을 수행하였다. 방사선 탐지기는 콘형 납 콜리메이터(Collimator)와 가시광 변환용 신틸레이터(CsITl) 및 차폐체로 구성된 센서부와 제어 및 방사광 신호처리를 수행하는 PC부로 구성된다. 감마방사선($^{60}Co$) 방사선장 실증시험에서 방사선원간 거리 83cm에서 측정된 거리 탐지는 5.3%의 오차로 확인되었다. 이 방사선 탐지기는 임의의 고방사선 누출사고에 대한 초기대응 작업을 수행하기 위한 무인 이동로봇용 방사선 탐지기로 활용이 가능하다.

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Application of the Detection of External Contamination on Radiation Workers for Bed Type Whole Body Counting Using Monte Carlo Method (몬테카를로 방법을 적용한 bed type 전신계측기의 방사선작업종사자 외부오염 검출 응용)

  • Kim, Jeong-In;Lee, Byoung-Il
    • Journal of Radiation Protection and Research
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    • v.38 no.4
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    • pp.242-245
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    • 2013
  • Monte Carlo method was applied to discriminate the external contamination on radiation workers in nuclear power plants for internal dose assessment generally used with a bed type scanning detector whole body counter. Korean voxel model with internal contamination was used to estimate the detection patterns of whole body scanning. Also, the BOMAB model with various external contamination was assumed to compare with detection of radionuclides inside the human body. From the comparison of detection efficiency between front and back side up, external contamination was easily distinguished.

Measurement of the Spatial Dose Rate for Distribution Room in Department of Nuclear Medicine (핵의학과 분배실 내의 공간선량률 측정)

  • Park, Jeong-Kyu;Cho, Euy-Hyun
    • Journal of Digital Contents Society
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    • v.13 no.2
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    • pp.151-157
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    • 2012
  • Even though the protective facility is well made with the development of medicine, the spatial dose within the radiation section could increase the exposure of the workers. The spatial dose is always present in distribution room within the Department of Nuclear Medicine, so the spatial dose of the interior distribution room is measured and analyzed for the prediction of the exposure dose. The spatial dose rate was $6.78{\pm}0.083{\mu}Sv/h$ in the $^{18}F$ distribution room of department of Nuclear Medicine, $9.248{\pm}0.013{\mu}Sv/h$ in $^{99m}Tc$, and $^{131}I$ distribution room. In addition, in case of $^{18}F$ distribution room, the yearly external exposure dose was $42.5{\mu}Sv$ when the nurse does IV in 1m in distance. It also showed that the spatial dose rate on the direction of right oblique showed higher than others by the standard of distribution window of distribution room. Therefore, the staying time of the workers should be short during distributing radiopharmaceuticals in the distribution room and the design of the distribution protection is necessary to reduce the exposure in the direction of right oblique of the protection. The utmost endeavors are required to reduce the worker's individual exposure dose while doing IV.