• Journal of Environmental Health Sciences
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• v.45 no.2
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• pp.99-112
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• 2019

Objective: This study aims to analyze the characteristics of airborne radon and thoron level ($Bq/m^3$) generated from household products containing monazites, and estimate the effective doses (mSv/yr). Method: Radon & Thoron detector EQF3220 was used to monitor real-time airborne radon and thoron level ($Bq/m^3$), and their daughters ($Bq/m^3$) were recorded every two hours. Effective doses (mSv/yr) for radon and thoron were estimated according to models developed by International Commission on Radiological Protection (ICRP) and United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). Results: The average levels of radon and thoron were $87.8Bq/m^3$ (range; $20.8-156.3Bq/m^3$) and $1,347.5Bq/m^3$ (range; $4-5,839.7Bq/m^3$), respectively. The average equilibrium factors (F) were 0.23 and 0.007, respectively. The levels of radon progeny were far higher than that thoron. Latex mattress showed the highest F (0.38). The average effective doses were estimated to be ICRP (1.9 mSv/yr) and UNSCER (1.3 mSv/yr) for radon and UNSCEAR (1.6 mSv/yr) for thoron. Conclusions: Our results have far exceeded the allowable effective dose for general population (1 mSv/yr). The government's actions such as the ban of use of consumer products containing monazite and the establishment of surveillance system to evaluate health effects for the people affected should be taken as early as possible.

• Journal of Korean Society of Occupational and Environmental Hygiene
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• v.29 no.1
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• pp.57-68
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• 2019

Objective: The purpose of this study is to propose the benefits of reduction measures according to the occupational radon reference level in order to present basic data for radon management guidelines considering domestic circumstances. Methods: This study uses radon data measured in the subway stations from 2015 to 2016. Of the total of 4,643 cases, 4,231 cases were analyzed excluding the 412 cases where the values were below $300Bq/m^3$. Results: Cost-Benefit analysis was done on the results of the field survey on subway work sites. At the exposure level of $400Bq/m^3$, the ratio between the cost and the benefit was highest at 1 : 1.81(the cost was KRW 1,398,568,032, while the benefit KRW 2,5248,772,841). At the exposure level of $600Bq/m^3$, the ratio of cost and benefit was 1: 1.80, at $300Bq/m^3$ it was 1.72, at $800Bq/m^3$ it was 1.71, at $200Bq/m^3$ it was 1.54, and at $100Bq/m^3$ it was 1.40. Conclusions: Radon management in the workplace provides economic benefits and appropriate reduction strategies are needed. In addition, it is necessary to establish and distribute radon exposure assessment procedures and guidelines for the safety and health of employees when exceeding the exposure standard, and guidelines for radon management in the workplace should be established.

• Journal of Radiation Protection and Research
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• v.38 no.2
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• pp.68-77
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• 2013

Derived Investigation levels(DILs) were calculated to protect the workers from the effects of both radiological hazard and chemical toxicity by uranium intake. Investigation Levels(ILs) of committed effective dose of 2 mSv $y^{-1}-6$ mSv $y^{-1}$ and uranium concentration of 0.3 ${\mu}g$ $g^{-1}$ in kidney, based on Korean Nuclaer Safety Act, Korean Occupational Safety and Health Act and current scientific studies of uranium intake were assumed. DILs of radiological hazard and chemical toxicity were then calculated based on the concentration of uranium in air of workplace, the lung monitoring and urine analysis, respectively. As a result, in case of the nuclear fuel fabrication plant where 3.5% enriched uranium is handled, derived investigation level(DIL) for the control of the concentration of uranium in the air of workplace assumed with 15-min acute inhalation was 0.6 mg $m^{-3}$ for all types of uranium. DILs for the control of the average concentration of uranium in air of workplace, assuming an 8-hour workday, were 15.21 ${\mu}g$ $m^{-3}$ of Type F uranium, 0.41-1.23 Bq $m^{-3}$ and 0.13-0.39 Bq $m^{-3}$ for Type M and Type S uranium, respectively. DILs for the lung monitoring assumed with a period of 6-month interval were 0.37-1.11 Bq and 0.39-1.17 Bq in acute and chronic inhalation for Type M, respectively and 0.30- 0.91 Bq and 0.19-0.57 Bq in acute and chronic inhalation for Type S, respectively. Since a detection limit of typical germanium detector for the measurement of 235U activity is 4 Bq, DILs calculated for the lung monitoring were not appropriate. DILs for urine analysis, for which an interval was assumed to be 1 month, were 14.57 ${\mu}g$ $L^{-1}$ based on chemical toxicity after acute inhalation. In addition, acute and chronic inhalation of Type M were calculated 2.85-8.58 ${\mu}g$ $L^{-1}$ and 1.09-3.27 ${\mu}g$ $L^{-1}$ based on the radiological hazard, respectively.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.2
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• pp.179-186
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• 2006

Chemical wastes are generated from nuclear facilities and R&D laboratories, but the uranium concentration in the final dried cake is evaluated into 11.2 Bq/g, which exceeds the exemption level of 10 Bq/g for each U isotopes, so the cake is categorized into a radioactive waste. Acid dissolution was applied to extract uranium from the waste sludge, and uranium adsorption on the dissolved solution was experimented by using IRN-77 and Diphosil bead. A large amount of resin was required to get above 80% of uranium removal, which was found to be due to a large amount of metal ions simultaneously dissolved from the precipitates with uranium. As an alternative method, acid dissolution is applied to the dewatered wet cake of the sludge, and the natural evaporation method is adopted for the dissolved solution. The uranium concentration of the dissolved solution was estimated to be 6.97E-01 Bq/ml, and the specific activity of the final waste sheets is evaluated to be 4.3 Bq/g. These results lead to the suggestion that the application of acid dissolution to the wet cake and the natural evaporation for the dissolved solution is an effective treatment method for chemical wastes containing uranium.

• Journal of Radiation Protection and Research
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• v.32 no.3
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• pp.97-104
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• 2007

The corelation between the indoor volume and the measured radon concentration has been analyzed by comparing the radon concentration and the indoor volume of apartment rooms in Jeonju City. We also measured the annual exposure dose based on the variation in indoor radon concentration over time. To do this, we took 8 larger rooms and 8 smaller rooms of apartment, respectively, as a sample. The average volume of the larger rooms and that of the smaller rooms were $31.59\;m^3$ and $16.82\;m^3$, respectively. The average radon concentration of the larger rooms and that of the smaller rooms turned out to be $71.73\;Bq/m^3$ and $108.51\;Eq/m^3$, respectively. indicating that indoor volume is in inverse proportion to the radon concentration, i.e., the bigger the ratio of the surface area/volume, the higher the indoor radon concentration. From the measurement of the variation in indoor radon concentration over time fur a single day, the average intraday radon concentration variation was found to be about $46.8\;Bq/m^3$. The highest level of concentration ($114.5\;Bq/m^3$) was measured between 8 and 10 AM and the lowest level of concentration ($67.7\;Bq/m^3$) between 2 and 4 PM. The annual exposure dose turned out to be in the range of 0.3 mSv/yr to 2.16 mSv/yr, showing that the dose in some apartments exceeded 1.3 mSv/yr, the numerical value presented by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR).

• Journal of Radiation Protection and Research
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• v.37 no.3
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• pp.149-158
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• 2012

In this paper, we measured the variations of radon concentrations in groundwater using low-level Liquid Scintillation Counter (LSC), an instrument for analyzing the alpha and beta radionuclides at its 10 sites around the Kumjung-Gu, north-western of Busan. Optimization of Pulse Shape Analyzer (PSA) to determinate the highest value of figure of merit (FM) was decided using Quantulus 1200 LSC with radium-226 source, the optimal PSA level was shown in the range of 100 to 110. The results show that the Minimum Detectable Activity (MDA) of radon concentrations is 0.61 $Bq{\cdot}L^{-1}$ for 20 minutes in PSA level. We find that the average radon concentration in groundwater is high in granitic rock area and low in volcanic rock area. (Biotite granite : 191.39 $Bq{\cdot}L^{-1}$, Micro graphic granite : 141.88 $Bq{\cdot}L^{-1}$, Adamellite : 92.94 $Bq{\cdot}L^{-1}$, Andesite (volcanic) : 35.35 $Bq{\cdot}L^{-1}$). No significant seasonal variation pattern is observed from the long-term variation analysis from 10 selected sites. We have not seen the significant correlation of radon concentration to groundwater temperature, atmospheric temperature, atmospheric pressure and rainfall. The concentration variation is probably caused by more complex factors and processes.

• Journal of Korean Society of Occupational and Environmental Hygiene
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• v.33 no.2
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• pp.115-125
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• 2023

Objectives: This study was conducted to measure the level of radon in the air at a highway tunnel construction site in a gneiss area using the New Austrian Tunneling Method (NATM) and to evaluate exposure levels by occupation. Methods: Radon concentrations in the air were measured using E-PERM at points 300 m, 600 m, and 900 m from the tunnel entrance during the excavation and waterproofing work inside the tunnel. In addition, radon concentrations were measured during external excavation to compare with the inside of the tunnel. Personal exposure levels for major occupations including tunnel workers, construction equipment operators, waterproofers, shotcrete workers, and safety and health managers who participated in the construction were estimated using radon concentration measured in the work process area and working hours by occupation. Results: As a result of a total of 77 radon measurements, the geometric mean (GM) concentration was 71.1 Bq/m³, and the maximum concentration was 127.3 Bq/m³, which was below the indoor air quality criteria. Radon concentration by process decreased in the order of the tunnel excavation process (GM= Bq/m³, GSD=1.2), waterproofing process (GM=73.35 Bq/m³, GSD=1.2), and outside excavating process (GM=45.28 Bq/m³, GSD=1.2). Processes inside the tunnel were significantly higher than outside excavating processes (p<0.05). There was no statistically significant difference in radon concentration measured inside by distance from the tunnel entrance, but the innermost point of the tunnel, 900 m (GM=79.24 Bq/m³, GSD=1.27), measured the highest. Conclusions: The occupation with the highest individual exposure to radon was tunnel worker (64.16 Bq/m³), followed by construction equipment driver (64.04 Bq/m³) and waterproofer (63.13 Bq/m³).

• Kyungpook Mathematical Journal
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• v.45 no.2
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• pp.161-166
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• 2005

Let BQ be the class of all semigroups whose bi-ideals are quasi-ideals. It is known that regular semigroups, right [left] 0-simple semigroups and right [left] 0-simple semigroups belong to BQ. Every zero semigroup is clearly a member of this class. In this paper, we characterize when generalized full transformation semigroups and generalized Baer-Levi semigroups are in BQ in terms of the cardinalities of sets.

• Progress in Medical Physics
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• v.14 no.1
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• pp.51-53
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• 2003

The results of the measured specific activities of Rn-222 in water for public water supply pump houses (wells) of Ulaanbaatar City, Mongolia using the HP-Ge gamma-spectrometer, are described. The average of the specific radioactivies for the Rn-222 were for the station “Centre” 82.59 Bq/l, station “Combinat” 91.35 Bq/l and station “Makh” 158.25 Bq/l, respectively.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05a
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• pp.919-924
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• 1995

사람이 숨을 쉬는 동안에 대기중에 포함된 C-14이 인체내에 흡수되는 경로를 살펴보았으며 이로부터 호흡경로를 통한 C-14의 체내 흡수량을 평가하였는데, 호흡중 C-14이 체내에 흡수되는 속도는 다음과 같이 구해졌다. $Q_{i}$(mBq/min)=7.250C$_{a.in}$ - 0.87 여기서 $C_{a,in}$ 은 공기중에 포함된 이산화탄소중의 C-14 농도(mBq/$m\ell$$CO_2$)이다. 이를 토대로 백그라운드 준위보다 약 10,000배 높은 작업환경(400 Bq/$m^2$)에서 8시간 동안 방사선작업을 수행하였을 경우 방사선 작업자는 일반인에 비해 약 4,100 Bq의 C-14 방사능을 추가로 섭취하게 되고, 이로 인해 작업자가 받게 될 체내 피폭선량은 약 0.06 mrem이었다.