• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2018년도 춘계 학술논문 발표대회
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• pp.230-231
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• 2018

Recently, the danger for radioactive materials has become a hot topic. Beginning with the Chernobyl nuclear accident in 1996, in 2011, the Fukushima nuclear power plant in Japan suffered major damage such as large-scale casualties and radioactive dangerous area selection. Concerns about leakage of radioactive materials due to recent earthquakes have been deepening in Korea, such as Wolsong Nuclear Power Plant in Gyeongju, and there is a growing interest in the safety of radioactive materials through the media and the media. However, the route to exposure to radioactive materials is not limited to these large-scale nuclear accidents. Typical examples of this are radioactive substances exposed in daily life. In the case of radon gas, the danger is being revealed through current events programs and news, and natural radiation exposure is attracting attention.

• Nuclear Engineering and Technology
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• 제54권10호
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• pp.3849-3854
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• 2022

The present work aims to optimize the radiation protection efficiency for ion-selective containers used in the liquid treatment for the nuclear power plant (NPP) cooling cycle. Some naturally occurring rocks were examined as filler materials to reduce absorbed dose and equivalent dos received from the radioactive waste container. Thus, the absorbed dose and equivalent dose were simulated at a distance of 1 m from the surface of the radioactive waste container using the Monte Carlo simulation. Both absorbed dose and equivalent dose rate are reduced by raising the filler thickness. The total absorbed dose is reduced from 7.66E-20 to 1.03E-20 Gy, and the equivalent dose is rate reduced from 183.81 to 24.63 µSv/h, raising the filler thickness between 0 and 17 cm, respectively. Also, the filler type significantly affects the equivalent dose rate, where the redorded equivalent dose rates are 24.63, 24.08, 27.63, 33.80, and 36.08 µSv/h for natural rocks basalt-1, basalt-2, basalt-sill, limestone, and rhyolite, respectively. The mentioned results show that the natural rocks, especially a thicker thickness (i.e., 17 cm thickness) of natural rocks basalt-1 and basalt-2, significantly reduce the gamma emissions from the radioactive wastes inside the modified container. Moreover, using an outer cementation concrete wall of 15 cm causes an additional decrease in the equivalent dose rate received from the container where the equivalent dose rate dropped to 6.63 µSv/h.

• 방사성폐기물학회지
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• 제11권2호
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• pp.133-156
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• 2013

자연유사연구는 방사성폐기물의 지하 처분에서 안전성평가를 포함하는 다중의 안전성 확보를 요구하는 safety case에서 중요한 역할을 담당하고 있다. 본 연구에서는 해외의 자연유사연구 동향을 조사하여, 처분장 재료물질들과 핵종이동 및 지연과 관련된 자연유사연구 결과들을 연구주제별로 정리하고, 주요 연구결과와 문제점, 결과의 활용성 등에 초점을 두고 분석하였다. 아울러 국내에서 수행된 자연유사연구 결과들을 우라늄 광상 연구, 암반을 이용한 연구, 지하수를 이용한 연구, 고고학적 유물을 이용한 연구 등으로 분류하고, 그 주요 결과들을 정리하였다. 지난 수 십 년 동안 수행되어 온 방대한 양의 자연유사연구 결과들이 존재하지만, 처분안전성 평가와 safety case 개발에 적극적으로 활용되지 못하였다. 따라서 본 연구에서는 자연유사연구 결과의 활용방법을 정리하고, 활용성을 증진하기 위한 방법론을 검토하였다. 방사성폐기물 처분장에 대한 안전성 평가의 신뢰성을 증진하고 검증하기 위해서는 자연유사연구의 수행은 필수적이다. 따라서 자연유사연구 결과들을 safety case 개발에 활용하기 위해서는 자연유사 정보 데이터베이스의 구축과 함께 활용방법론이 개발되어야 할 필요가 있다.

• 지질공학
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• 제24권4호
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• pp.535-550
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• 2014

지하수내 존재하고 있는 자연방사성물질인 우라늄과 라돈-222의 산출특성과 지화학적 기원을 알아보기 위해 괴산지역 연구부지내 120 m 깊이의 지하수 관정을 시추하여 심도별 시추코어의 암석화학적 특성과 지하수의 화학적 특성을 분석하였다. 시추코어 샘플 분석과 함께 더블패커시스템과 베일러를 이용하여 8개의 심도별 지하수 시료를 채취하여 지화학적 특성 분석을 수행하였다. 시추코어 분석결과, 주요 암종은 화강반암과 점판암이었으며 일부 구간에서는 탄산염암과 석회규산염암, 페그마타이트가 확인되었다. 심도별 지하수의 pH는 7.8~8.4의 범위이며, 화학적 유형은 Na-$HCO_3$형태를 보였다. 암석 및 광물 내 우라늄과 토륨의 함량은 각각 < 0.2~14.8 ppm과 0.56~45.0 ppm의 범위였으며, 암석현미경과 전자현미경(EPMA) 관찰 결과 자연방사성원소(우라늄) 함유 광물은 흑운모내 포획된 모나자이트 광물인 것으로 확인되었다. 우라늄은 이들 광물의 주요 구성원소를 치환하여 존재하는 것으로 보이며 파쇄대와 같은 주요 대수층 구간에서 용해되어 지하수와 함께 용출되는 것으로 보인다. 라돈-222의 함량은 우라늄의 함량과 어떠한 상관성을 보이지 않았으며 향후, 라돈가스 기원 추적을 위해서는 헬륨과 네온 등 영족기체 동위원소비를 이용한 간접적인 방법을 적용하여 분석할 필요가 있을 것으로 판단된다.

• Journal of Radiation Protection and Research
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• 제41권3호
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• pp.291-300
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• 2016

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.

• 방사선산업학회지
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• 제10권4호
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• pp.173-179
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• 2016

Coals and coal ashes, raw materials and by-products, in coal-fired power plants contain naturally occurring radioactive materials (NORM). They may give rise to internal exposure to workers due to inhalation of airborne particulates containing radioactive materials. It is necessary to characterize radioactivity concentrations of the materials for assessment of radiation dose to the workers. The objective of the present study was to analyze radioactivity concentrations of coals and by-products at four coal-fired plants in Korea. High purity germanium detector was employed for analysis of uranium series, thorium series, and potassium 40 in the materials. Radioactivity concentrations of $^{226}Ra$, $^{228}Ra$, and $^{40}K$ were $2{\sim}53Bq\;kg^{-1}$, $3{\sim}64Bq\;kg^{-1}$, and $14{\sim}431Bq\;kg^{-1}$ respectively in coal samples. For coal ashes, the radioactivity concentrations were $77{\sim}133Bq\;kg^{-1}$, $77{\sim}105Bq\;kg^{-1}$, and $252{\sim}372Bq\;kg^{-1}$ in fly ash samples and $54{\sim}91Bq\;kg^{-1}$, $46{\sim}83Bq\;kg^{-1}$, and $205{\sim}462Bq\;kg^{-1}$ in bottom ash samples. For flue gas desulfurization (FGD) gypsum, the radioactivity concentrations were $3{\sim}5Bq\;kg^{-1}$, $2{\sim}3Bq\;kg^{-1}$, and $22{\sim}47Bq\;kg^{-1}$. Radioactivity was enhanced in coal ash compared with coal due to combustion of organic matters in the coal. Radioactivity enhancement factors for $^{226}Ra$, $^{228}Ra$, and $^{40}K$ were 2.1~11.3, 2.0~13.1, and 1.4~7.4 for fly ash and 2.0~9.2, 2.0~10.0, 1.9~7.7 for bottom ash. The database established in this study can be used as basic data for internal dose assessment of workers at coal-fired power plants. In addition, the findings can be used as a basic data for development of safety standard and guide of Natural Radiation Safety Management Act.

• Nuclear Engineering and Technology
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• 제56권2호
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• pp.707-714
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• 2024

Different degrees of natural radioactivity found in quartz can have negative consequences on health. Quartz vein along the investigated Abu Ramad area, Egypt, had its natural radioactivity assessed. The HPGe spectrometer was used to determine the role played by the radionuclides ²³⁸U, ²³²Th, and ⁴⁰K in the gamma radiation that was emitted, and the results showed that these concentrations are 484.64 ± 288.4, 36.8 ± 13.1 and 772.2 ± 134.6 Bq kg^-1 were higher than the corresponding reported global limits of 33, 45, and 412 Bq kg^-1 for each radionuclide (²³⁸U, ²³²Th, and ⁴⁰K). Among the radiological hazard parameters, the excess lifetime cancer risk (ELCR) is estimated and it's mean value of ELCR (1.2) is higher than the permissible limit of 0.00029. The relationship between the radionuclides and the associated radiological hazard characteristics was investigated based on multivariate statistical methods including Pearson correlation, principal component analysis (PCA), and hierarchical cluster analysis (HCA). According to statistical research, the radioactive risk of quartz is primarily caused by the ²³⁸U, ²³²Thand ⁴⁰K. Finally, applying quartz to building materials would pose a significant risk to the public.

• Journal of Radiation Protection and Research
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• 제41권2호
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• pp.133-140
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• 2016

Backgrounds: The accident at Fukushima Daiichi Nuclear Power Plant (NPP), March 2011, caused serious radioactive contamination over wide area in east Japan. Therefore, it is important to know the effect of the accident and the status of NPP. Materials and Methods: This paper provides a review on the status of radiation dose and radioactive contamination caused by the accident on the basis of publicized information. Results and Discussion: Monitoring of radiation dose and exposure dose of residents has been conducted extensively by the governments and various organizations. The effective dose of general residents due to the accident proved to be less than a mSv both for external and internal dose. The equivalent committed dose of thyroid was evaluated to be a few mSv in mean value and less than 50 mSv even for children. Monitoring of radioactivity concentration has been carried out on food ingredients, milk and tap water, and actual meal. These studies indicated the percentage of foods above the regulation standard was over 10% in 2011 but decreasing steadily with time. The internal dose due to foods proved to be tens of ${\mu}Sv$ and much less than that due to natural $^{40}K$ even in the Fukushima area and decreasing steadily, although high level concentration is still observed in wild plants, wild mushrooms, animals and some kind of fishes. Conclusion: According to extensive studies, not only the effect of the accident but also the pathway and countermeasures against radioactive contamination have been revealed, and they are applied very effectively for restoration of environment and reconstruction of the area.

• Nuclear Engineering and Technology
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• 제54권11호
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• pp.4005-4012
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• 2022

As high-level radioactive waste (HLW) generated from nuclear power plants is harmful to the human body, it must be safely disposed of by an engineered barrier system consisting of disposal canisters and buffer and backfill materials. A gap exists between the canister and buffer material in a HLW repository and between the buffer material and natural rock-this gap may reduce the water-blocking ability and heat transfer efficiency of the engineered barrier materials. Herein, the basic characteristics and thermal properties of granular bentonite, a candidate gap-filling material, were investigated, and their effects on the temperature change of the buffer material were analyzed numerically. Heat transfer by air conduction and convection in the gap were considered simultaneously. Moreover, by applying the Korean reference disposal system, changes in the properties of the buffer material were derived, and the basic design of the engineered barrier system was presented according to the gap filling material (GFM). The findings showed that a GFM with high initial thermal conductivity must be filled in the space between the buffer material and rock. Moreover, the target dry density of the buffer material varied according to the initial wet density, specific gravity, and water content values of the GFM.

• 자원환경지질
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• 제53권5호
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• pp.565-583
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• 2020

최근 생활용품 및 건축자재 등에서 검출된 자연 방사성 물질로 인해 사회적으로 다양한 문제가 발생하고 있으며, 이는 조속히 해결해야 될 사회현안으로 대두되고 있다. 우리나라에서도 토양이나 지하수 내 중금속 및 우라늄, 라돈 등의 자연방사성 물질에 대해서 환경부에 의해 지난 20년 이상 장기간 조사된 바 있고, 토양과 지하수 내 자연방사성 물질의 기원이 암석-성인-변형적 특성 등의 지질학적 요인들과 밀접한 상관관계를 보여주는 것으로 추정되고 있지만, 기반암, 기반암 상부토양 및 지하수가 발달한 단층계 내 자연방사성 물질의 국가배경농도가 수립되어 있지 않아 정확한 지질학적 상관관계 규명이 미흡한 실정이다. 본 연구에서는 국내 현생 심성암류의 성인과 천연 방사성(라돈, 우라늄, 토륨 등)물질 농도와의 상관관계에 대한 예비 연구를 수행하였다. 현생 심성암류 중 알칼리 화강암류(섬장암, 몬조니암, 몬조섬록암 및 알칼리화강암)는 높은 마그마 온도와 고알칼리성의 경향 때문에 U, Th, Zr, REE 및 Nb 등이 부화되는 특징을 보여주어 높은 U과 Th 농도를 가진다. 지각물질의 혼합에 의해 고분화된 화강암류(우백질 화강암, 복운모화강암, 고알루미형질 S-type 화강암 및 페그마타이트)는 고분화되지 않은 일반 화강암류(섬록암, 화강섬록암 및 화강암)보다 U, Th 및 K+Na이 더욱 부화되는 경향을 보여준다. 고알칼리성 화강암류들은 주로 판내부의 열개환경, 대륙충돌 조산작용과 해양판의 대륙판 아래 섭입 이후에 일어나는 확장환경에서 생성된다. 반면에 우리나라에서 주로 산출되는 아알칼리성 캘크알칼리 화강암류는 해양판의 대륙판 밑으로의 섭입에 의한 호환경에서 주로 생성된다. 결과적으로 국내 현생 심성암류의 U, Th 및 K 함량변화는 지구조 환경에 의한 암석성인과 밀접한 연관성을 가지는 것으로 추정되며, 현생화강암류 대한 감마분석 자연방사성 핵종(²²⁶Ra, ²³²Th 및 ⁴⁰K) 예비 결과들은 고알칼리성과 고분화된 화강암류에서 높은 값을 보여준다.