Development of Internal Dose Assessment Procedure for Workers in Industries Using Raw Materials Containing Naturally Occurring Radioactive Materials

Choi, Cheol Kyu; Kim, Yong Geon; Ji, Seung Woo; Koo, Boncheol; Chang, Byung Uck; Kim, Kwang Pyo

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자료유형: 학술저널

저자정보: Choi, Cheol Kyu (College of Engineering, Kyung Hee University) Kim, Yong Geon (College of Engineering, Kyung Hee University) Ji, Seung Woo (College of Engineering, Kyung Hee University) Koo, Boncheol (Korea Institute of Nuclear Safety) Chang, Byung Uck (Korea Institute of Nuclear Safety) Kim, Kwang Pyo (College of Engineering, Kyung Hee University)

저널정보: 대한방사선방어학회 방사선방어학회지 방사선방어학회지 제41권 제3호

발행연도: 2016.1

수록면: 291 - 300 (10page)

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연구주제

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연구배경

🔬

연구방법

🏆

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Background: It is necessary to assess radiation dose to workers due to inhalation of airborne particulates containing naturally occurring radioactive materials (NORM) to ensure radiological safety required by the Natural Radiation Safety Management Act. The objective of this study is to develop an internal dose assessment procedure for workers at industries using raw materials containing natural radionuclides. Materials and Methods: The dose assessment procedure was developed based on harmonization, accuracy, and proportionality. The procedure includes determination of dose assessment necessity, preliminary dose estimation, airborne particulate sampling and characterization, and detailed assessment of radiation dose. Results and Discussion: The developed dose assessment procedure is as follows. Radioactivity concentration criteria to determine dose assessment necessity are $10Bq{\cdot}g^{-1}$ for $^{40}K$ and $1Bq{\cdot}g^{-1}$ for the other natural radionuclides. The preliminary dose estimation is performed using annual limit on intake (ALI). The estimated doses are classified into 3 groups ( < 0.1 mSv, 0.1-0.3 mSv, and > 0.3 mSv). Air sampling methods are determined based on the dose estimates. Detailed dose assessment is performed using air sampling and particulate characterization. The final dose results are classified into 4 different levels ( < 0.1 mSv, 0.1-0.3 mSv, 0.3-1 mSv, and > 1 mSv). Proper radiation protection measures are suggested according to the dose level. The developed dose assessment procedure was applied for NORM industries in Korea, including coal combustion, phosphate processing, and monazite handing facilities. Conclusion: The developed procedure provides consistent dose assessment results and contributes to the establishment of optimization of radiological protection in NORM industries.

#Naturally occurring radioactive material #NORM) #Internal dose #Dose assessment procedure #Air sampling

참고문헌 (18)

참고문헌 신청

International Atomic Energy Agency / 2006 / Assessing the need for ra diation protection measures in work involving minerals and raw materials :11~26

International Atomic Energy Agency / 2007 / Radiation protection and NORM residue management in the zircon and zirconia industries :51~61

International Atomic Energy Agency / 2011 / Radiation Protection and NORM Residue Management in the Production of Rare Earths from Thorium Containing Minerals :97~112

International Atomic Energy Agency / 2012 / Radiation protection and NORM residue management in the titanium dioxide and related industries :62~74

Van der steen J / 2004 / Strategies and methods for optimisation of protection against internal exposures of workers from industrial natural sources (SMOPIE) :13~20

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