• Journal of Radiation Protection and Research
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• 제38권4호
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• pp.234-236
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• 2013

비밀봉 방사성물질을 취급하는 시설에서 이들 물질에 의한 작업환경의 다소간의 오염은 피할 수 없다. 오염의 우려가 있는 작업환경에서 오염관리의 일차적인 목적은 방사성물질의 잠재적 체내섭취로 인한 영향이다. 본 논문은 보수적 가정과 간단한 계산에 의거하여 공기오염에 따른 방사성물질의 공기중 농도와 흡입에 의한 연간 섭취량을 산출한 후, 관련 고시에서 정하는 유도공기중농도와 연간섭취한도와 비교함으로써 종사자의 내부피폭 정도를 평가하는 절차를 제공한다. 제시된 절차는 공기중 방사성물질 측정 및 내부피폭 감시의 필요성, 적합한 방호용구의 착용, 배기설비 설계를 위한 정보 획득 등 공기오염과 종사자의 내부피폭 감시를 위한 실무적 요건을 판단할 목적으로 활용될 수 있다.

• 방사선산업학회지
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• 제10권1호
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• pp.37-41
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• 2016

The recent prevalence of PET examinations in Korea has led to an increase in the number of cyclotrons. The medical isotope $^{18}F$ produced in most cyclotron facilities currently operating in Korea is emitted into the environment during the production of [$^{18}F$]FDG, a cancerdiagnosis reagent. The amount of [$^{18}F$]FDG synthesized determines the radioactive concentration of $^{18}F$ in the exhaust. At some facilities, this amount temporarily exceeds the emission limit. In this study, we evaluated the $^{18}F$ radioactivity concentration in the exhaust from the cyclotron facility at Chosun University. The $^{18}F$ radioactivity concentration was measured using an air sampler and a HPGe semiconductor detector. The measurements showed that the radioactive concentration of $^{18}F$ in the exhaust at the cyclotron facility at Chosun University was the highest during [$^{18}F$]FDG synthesis but remained under the legal limit of $2,000Bq\;m^{-3}$.

• 방사선산업학회지
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• 제18권2호
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• pp.147-153
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• 2024

Radioactive liquid waste generated during operation and overhaul is collected and reused through the radioactive liquid waste treatment system and continuous monitoring system in the nuclear power plant or discharged to the outside if it satisfies the limit within the control and monitoring. However, there are concerns about boric acid management, which controls the power output of nuclear power plants in radioactive liquid waste. Due to the behavior of boric acid, it is difficult to remove it in the existing liquid radwaste system, and the concentration of boric acid water discharged tends to be higher than the natural state of 5 ppm, so additional facilities should be considered. Therefore, this study aims to evaluate the radiological effects of radioactive waste treatment facilities that are under development and use them as a basis for managing worker exposure and evaluating the safety of facilities in the future.

• Nuclear Engineering and Technology
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• 제56권6호
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• pp.2239-2246
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• 2024

The present study aimed to assess the radioactive hazards associated with the application of granitoid rocks in building materials. An HPGe spectrometer was used to detect the levels of the radioactive elements uranium-238, thorium-232, and potassium-40 in the granitoid rocks. The results showed that the levels of these elements were lower (38.32 < 33 Bq kg^-1), comparable (47.19-45 Bq kg^-1) and higher (992.26 ≫> 412 Bq kg^-1) than the worldwide limits for ²³⁸U, ²³²Th, and ⁴⁰K concentration, respectively. The exposure to gamma radiation of granitoid rocks was studied by various radiological hazard variables like the absorbed dose rate (D_air), the outdoor and indoor annual effective dose (AED_out and AED_in), and excess lifetime cancer risk (ELCR). A variety of statistical methods, including Pearson correlation, principal component analysis (PCA), and hierarchical cluster analysis (HCA) was used, to study the relationship between the radioactive elements and the radiological hazards. According to statistical analysis, the main radioactive risk of granitoid rocks is contributed to by the elements uranium-238, thorium-232, and potassium-40. Granitoid rocks can be applied in building materials, but under control to prevent risk to the public.

• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2017년도 추계 학술논문 발표대회
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• pp.92-93
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• 2017

Recently, there has been an increasing interest in natural radioactive gas radon(Rn-222), the problem of indoor air quality pollution to worldwide. It has been scientifically proven to be hazardous to various diseases such as lung cancer and skin cancer if the human body is exposed to long-term accumulation of atomic nuclei due to the destruction of radon and alpha lines. Based on the indoor air quality control policy, this study is a basic experiment in the manufacture of a selective elimination function to containing radon adsorption and reduction of radon concentration, which is used to absorb radioactive isotopes such as phosphorus and radon in indoor environment.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1830-1837
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• 2023

The thermal cutting of contaminated or activated metals during decommissioning nuclear power plants inevitably results in the release of radioactive aerosol. Since radioactive aerosols are pernicious particles that contribute to the internal dose of workers, air conditioning units with a HEPA filter are used to remove radioactive aerosols. However, a HEPA filter cannot be used permanently. This study evaluates the efficiency and lifetime of filters in actual metal cutting condition using a plasma arc cutter and a high-resolution aerosol detector. The number concentration and size distribution of aerosols from 6 nm to 10 ㎛ were measured on both the upstream and downstream sides of the filter. The total aerosol removal efficiency of HEPA filter satisfies the standard of removing at least 99.97% of 0.3 ㎛ airborne particles, even if the pressure drop increases due to dust feeding load. The pressure drop and particle size removal efficiency at 0.3 ㎛ of the HEPA filter were found to increase with repeated cutting experiments. By contrast, the efficiency of used HEPA filter reduced in removing nano-sized aerosols by up to 79.26%. Altogether, these results can be used to determine the performance guidance and replacement frequency of HEPA filters used in nuclear power plants.

• 한국의학물리학회지:의학물리
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• 제27권3호
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• pp.156-161
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• 2016

When air discharged from a radioisotope production facility is contaminated with radiation, the public may be exposed to radiation. The objective of this study is to manage such radiation exposure. We measured the airborne radioactivity concentration at a 30 MeV cyclotron radioisotope production facility to assess whether the exhaust gas was contaminated. Additionally, we investigted the radioactive contamination of the air filter for efficient air purification and radiation safety control. To measure the airborne radiation concentration, specimens were collected weekly for 4 h after the beginning of the radioisotope production. Regarding the air purifier, five specimens were collected at different positions of each filter-pre-filter, high-efficiency particulate air filter, and charcoal filter-installed in the cyclotron production room. The concentrations of F-18, I-123, I-131, and Tl-201 generated in the radioiodine production room were $13.5Bq/m^3$, $27.0Bq/m^3$, $0.10Bq/m^3$, and $11.5Bq/m^3$, respectively; the concentrations of F-18, I-123, and I-131 produced in the radioisotope production room were $0.05Bq/m^3$, $16.1Bq/m^3$, and $0.45Bq/m^3$, correspondingly; and those of F-18, I-123, I-131, and Tl-201 generated in the accelerator room were $2.07Bq/m^3$, $53.0Bq/m^3$, $0.37Bq/m^3$, and $0.15Bq/m^3$, respectively. The maximum radiation concentration of I-123 generated in the radioiodine production room was 1,820 Bq/g, which can be disposed after 2 days. The maximum radiation concentration of Tl-202 generated in the radioisotope production room was 205 Bq/g, and this isotope must be stored for 53 days. The I-123 generated in the radioiodine production room had a maximum concentration of 1,530 Bq/g and must be stored for 2 days. The maximum radiation concentration of Na-22 generated in the radioisotope production room was 0.18 Bq/g and this isotope must be disposed after 827 days. To manage the exhaust, the efficiency of air purification must be enhanced by selecting an air purifier with a long life and determining the appropriate replacement time by examining the differential pressure through systematic measurements of the airborne radiation contamination level.

• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2018년도 춘계 학술논문 발표대회
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• pp.226-227
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• 2018

Recently, as the interest of the government and the public on energy saving has increased, the airtightness of buildings has been improved to improve the insulation performance of buildings. However, indoor air pollution due to increase of pollution source in indoor space and lack of ventilation is increasing and interest in indoor air quality is increasing. In 2003, the Ministry of Environment enacted and promulgated the Act on Indoor Air Quality Control in Multi-use Facilities. Radon is a naturally occurring radioactive inert gas with colorless, tasteless and odorless nature. The concentration is high in a room where radon can not escape. Although lononggas is naturally occurring, it is not interested in living environment, but it is easily inhaled through human body through respiration and causes lung cancer in long-term exposure. Therefore, this study intends to carry out an experiment for the reduction of radon gas, which is the first carcinogen in indoor air pollution sources.

• 한국철도학회논문집
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• 제3권2호
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• pp.62-67
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• 2000

Modern people stay at indoor places about 90% of a day. Radon-222 is a gas produced by the radioactive decay of the element radium. And, radon is one of the major indoor air pollutants. Radon moves into the underground space through various routes and is considered to cause lung cancer by hurting the lung tissues. In this study, we measured the subway radon level at 9 stations of 3 lines. According to test results, we can figure out the concentration of radon by lines, times, and measuring points. So, it was found that ventilation conditions are the most important factors in the subway air quality. Finally, we suggested effective and economic management methods of air pollution in the subway.

• 핵의학기술
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• 제16권2호
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• pp.126-130
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• 2012

방사성의약품 제조 시 휘발성 기체의 경우에 완전 차폐가 되지 않고, Hot cell 외부로 그리고 배기덕트를 통해 작업자에게 외부피폭은 물론 호흡을 통해 내부피폭을 가져오게 한다. 처음에는 Hot cell 자체의 배출구를 막아서 방사성기체를 차단하려하였으나 장치에 맞는 기체 밀폐형 댐퍼의 제작이 어렵고, 크기가 맞지 않아서 설치 후에 여전히 문제점이 개선되지 않았다. 그러나 Tedlar gas sampling bag의 사용으로 합성 장치의 가스 배출구를 연결하여 방사성 기체를 저장하고 10반감기가 지난 후에 배출함으로써 작업자의 피폭을 확연히 줄이게 되었으며 $^{18}F$ 방사성 기체는 Hot cell 배출구에 활성탄 필터를 연결하고 최종 배출구에 2차 활성탄 필터를 사용함으로써 배출되는 방사능 농도를 90% 이상 줄여주었다. 단 반감기의 핵종인 경우는 위와 같은 경우를 이용하여 다음날 작업을 할 수 있지만 반감기가 긴 핵종들 같은 경우는 다음날 처리 할 수 없는 문제점들이 발생한다. Decay tank의 추가적인 문제점들을 보완하거나 기체상의 여러 방사성 입자들을 포집 할 수 있는 물질들이 만들어져야 할 것이다. 현재 우리나라는 최종 배출 공기 중 방사능 농도만을 규제하고 있으나 유럽 같은 경우 일일 배출 양과 연간 배출도 규제를 하고 있다. 방사성의약품 합성 시 발생하는 많은 방사성 물질들을 보다 효과적으로 친환경적으로 처리할 수 있는 여러 연구들이 이루어져야 할 것이다.