• Title/Summary/Keyword: Radioactive dose

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Calculation of Shielding Rate and Dose Distribution of Space of L-Block-Type Protective Equipment for Radioactive Fluorine using the Monte Carlo Method (몬테칼로 방법을 이용한 방사성 불소에 대한 L-블럭형 방호장비의 차폐율 및 공간의 선량분포 계산)

  • Han, Dong-Hyun
    • Journal of the Korean Society of Radiology
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    • v.15 no.6
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    • pp.813-819
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    • 2021
  • In this study, the shielding rate of L-block-type shielding equipment used for radiation protection when radioactive fluorine is injected into the human body and the dose distribution of the space in the injection room were calculated using the Monte Carlo method. The shielding rate of the body and window parts of the L-block-type shielding equipment was 99.99%. The dose distribution calculated at a distance of 1 m was relatively high at 135°, 45°, 225°, 315°, and 180° of the XZ plane, and was calculated to be very low at 0°, 90°, and 270°. In the YZ plane, it was relatively high at 135°, 180°, and 225°, and was calculated very low at the remaining angles. The AZ and BZ planes also showed similar results to the YZ plane. In addition, it was confirmed that the shielding rate was the best in the range of 225° to 315° through the dose distribution in the horizontal direction of the source and the 45° direction above the source. These results can be used as basic data necessary for radiation protection of radiation workers.

Important Radionuclides and Their Sensitivity for Ground water Pathway of a Hypothetical Near-Surface Disposal Facility

  • Park, J. W.;K. Chang;Kim, C. L.
    • Nuclear Engineering and Technology
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    • v.33 no.2
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    • pp.156-165
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    • 2001
  • A radiological safety assessment was performed for a hypothetical near-surface radioactive waste repository as a simple screening calculation to identify important nuclides and to provide insights on the data needs for a successful demonstration of compliance. Individual effective doses were calculated for a conservative ground water pathway scenario considering well drilling near the site boundary. Sensitivity of resulting ingestion dose to input parameter values was also analyzed using Monte Carlo sampling. Considering peak dose rate and assessment time scale, C-14 and T-129 were identified as important nuclides and U-235 and U-238 as potentially important nuclides. For C-14, the dose was most sensitive to Darcy velocity in aquifer The distribution coefficient showed high degree of sensitivity for I-129 release.

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Radiological safety evaluation of dismantled radioactive concrete from Kori Unit 1 in the disposal and recycling process

  • Lee, ChoongWie;Kim, Hee Reyoung;Lee, Seung Jun
    • Nuclear Engineering and Technology
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    • v.53 no.6
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    • pp.2019-2024
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    • 2021
  • For evaluating the radiological safety of dismantled concrete, the process of disposal and recycling of the radioactive concrete generated during the dismantling of Kori Unit 1 is analyzed. Four scenarios are derived based on the analysis of the concrete recycling and disposal process, and the potential exposure to the workers and public during this process are calculated. VISIPLAN and RESRAD code are used for evaluating the dosages received by the workers and public in the following four scenarios: concrete inspection, transport of concrete by the truck driver, driving on a recycled concrete road, and public living near the landfilled concrete waste. Two worker exposure scenarios in the processing of concrete and two public exposure scenarios in recycling and disposal are considered; in all the scenarios, the exposure dose does not exceed the annual dose limit for each representative.

Dose assessment applied with the specific data of Young-gwang area for clearance by landfill (영광지역 특성자료를 적용한 매립 자체처분 피폭선량 평가)

  • 임용규;이지훈;양호연;신상운
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.497-502
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    • 2003
  • Landfill is an widely applied alternative for clearance of non-contaminated waste or slightly contaminated waste generated from nuclear facilities. In this study, exposure dose is estimated for a worker and a resident at the landfill area in Young-gwang nuclear power plant. Based on evaluated dose, clearance concentrations of each radionuclide are determinated for dose criteria of 10 $\muSv/y$. The results of age-dependent dose are 1.02 $\muSv$ per year for resident and 0.471 $\muSv$ per year for worker. Clearance concentrations for each radionuclide are evaluated from $1.33{\times}10_{-1}$ Bq per gram to $2.85{\times}10^2$ Bq per gram.

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