• Proceedings of the Korean Radioactive Waste Society Conference
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• 2017.05a
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• pp.79-80
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• 2017

• The Korean Journal of Nuclear Medicine
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• v.7 no.2
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• pp.27-34
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• 1973

Pulmonary perfusion scan with radioactive $^{113m}In$-iron hydroxide particle was performed in the 25 cases of heart disease which had been diagnosed by cardiac catheterization prior to surgery from July, 1972 to July, 1973 at the Department of Radiology and Nuclear Medicine, Yonsei Medical College. It consists of 7 mitral stenosis, 2 mitral insufficiency, 1 aortic insufficiency, 3 atrial septal defect, 5 ventricular septal defect, 2 patent ductus arteriosus, 1 transposition of great vessel and 4 Tetralogy of Fallot. Findings of pulmonary perfusion scan in relation to hemodynamic data of cardiac catheterization were examined. 1) Out of 10 cases of acquired valvular heart disease, In 6 cases of mitral stenosis and 1 case of aortic insufficiency, radioactivity was increased at both upper lung. This finding is noted when pulmonary wedge or venous pressure was elevated above 22 mmHg and arterial systolic pressure above 33 mmHg. 2) Out of 15 cases of congenital heart disease. In almost all cases of atrial septal defect and ventricular septal defect except 2 cases, radioactivity was even at both entire lung. In 2 cases of patent ductus arteriosus, radioactivity was decreased especially at the left lung. It is observed that in acyanotic congenital heart disease, radioactivity of lung is not related with pulmonary arterial pressure. In 3 cases of Tetralogy of Fallot, radioactivity was even at both entire lung and in 2 of them, extrapulmonary radioactivity of liver or kidney which depends on size of defect and volume of right to left shunt reversible, was noted.

• Journal of Environmental Science International
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• v.15 no.7
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• pp.689-694
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• 2006

To examine inshore radioactive contamination caused by nuclear power plants, nuclear testing, hospital and laboratory, both gross ${\beta}$-radioactivity and ${\upsilon}$-spectrometry were measured. The measurements were taken with the Abalone and Top shell, which had been collected from the four different sites at the coast in Jeju-do (Seongsan, Deajeong, Wimi, Dodu). The activity ranges of concentration were respectively 0.11-0.29 Bq/kg-wet for $^{90}Sr$, 0.01-0.04 Bq/kg-wet for $^{137}Cs$, 36 - 53 Bq/kg-wet for $^{40}K$ in shellfish on the Jeju island. The radioactivities of $^{90}Sr$, $^{137}Cs$ and $^{40}K$ were similar to those in sampling location of shellfish in the coastal on the Jeju island. The radioactivity of $^{90}Sr$ for the Abalone was lower level than that for Top shell. The radio- activity of $^{137}Cs$ for the Abalone was similar to that for the Top shell. But the radioactivity of $^{40}K$ for the Abalone was higher level than that for the Top shell. As a result, the gross ${\beta}$-radioactivity observed was similar to that in nature. Among radionuclides, only $^{90}Sr$, $^{137}Cs$ and $^{40}K$ were detected in a very small amount, and each was also close to the natural levels.

• Journal of radiological science and technology
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• v.44 no.3
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• pp.247-252
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• 2021

As the number of single-person households increases, the consumption of bottled water is increasing. In addition, as the public's interest in radioactivity increases, interest in the field of living radioactivity is also increasing. Since drinking water is an essential element in our daily life, it must be safe from radioactivity. In this study, gamma radiation of drinking spring water was measured and internal exposure dose evaluation was performed to determine its harmfulness. K-40 and uranium-based radioactivity analysis was performed through a high-purity germanium detector, and as a result, drinking water was detected somewhat higher than that of mixing water. Since there is no regulation on the natural radioactivity concentration in Korea, it was compared with the U.S. Environmental Protection Agency Drinking Water Regulations and World Health Organization standard. As a result, there were some items that exceeded standards. Internal exposure was evaluated according to the effective dose formula of ICRP 119. As the result was derived that a maximum of 1.17 mSv per year could be received. This result means that the dose limit for the general public may be exceeded, and it was judged that it is necessary to set an appropriate standard value and present a recommendation value through continuous monitoring in the future.

• Journal of Radiation Protection and Research
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• v.20 no.1
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• pp.8-15
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• 1995

An estimate of a change in radioactivity's circumstances around the nuclear power plant is validated with the results of the radioactivity measurements are compared. In this study, to further enhance the reliability of the results obtained from the environmental radioactivity measurements and analysis around the nuclear power plants that have been carried out up to the present. In the korea standard, there is the technical analysis guide for general stable chemical element's, but there is not the technical analysis guide for the radionuclei. therefore the environmental sample collection, the pretreatment of the sample and radionuclide analysis in the sample, the result's of the environmental radioactivity measurements by each organization, etc. are different. It is not sufficient for the database to forecasting a change in radioactivity's circumstances. A comparative study of collection and pretreatment techniques for the soil sample, the results by comparison, the method of minimizing the relative error are proposed. At one side of sample collection, there are going to considered that the surroundings of sample collection like the lay of the land, the provision of the selection standard for the area and pathway of radionuclide adhesion, the coherence of sample collection, etc.. at another side of pretreatment of the sample and measurement in the case of soil sample, how to do homogeneously the soil particle size and the standard tools, i.e. kinds of meshes, must to be selected.

• Analytical Science and Technology
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• v.30 no.5
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• pp.252-261
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• 2017

Naturally occurring radioactive materials (NORMs) increase radiation exposure to the public as these materials are concentrated through artificial manufacturing processes by human activities. This study focuses on the development of a method for the quantitative analysis of $^{232}Th$, $^{235}U$, and $^{238}U$ in building materials. The accuracy and precision of inductively coupled plasma mass spectrometry (ICP-MS) for determination of digestion processes was evaluated for certified reference materials (CRMs) digested using various mixed acid (e.g., aqua regia, hydrofluoric acid, and perchloric acid) digestions and a $LiBO_2$ fusion method. The method validation results reveal that a $LiBO_2$ fusion and $Fe(OH)_3$ co-precipitation should be applied as the optimal sample digestion process for the quantitative analysis of radionuclides in building materials. The radioactivity of $^{232}Th$, $^{235}U$, and $^{238}U$ in a total of 51 building material (e.g., board, brick, cement, paint, tile, and wall paper) samples was quantitatively analyzed using an established process. Finally, the values of $^{238}U$ and $^{232}Th$ radioactivity were comprehensively compared with those from the indirect method using ${\gamma}$-spectrometry.

• Journal of Radiation Protection and Research
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• v.44 no.3
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• pp.118-126
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• 2019

Background: Government conducts environmental radioactivity surveillance for verification purpose around nuclear facilities based on the Nuclear Safety Law and issues a surveillance report every year. This study aims to evaluate the short and the long-term fluctuation of radionuclides detected above MDC and their origins using concentration ratios between these radionuclides. Materials and Methods: Sample media for verification surveillance are air, rainwater, groundwater, soil, and milk for terrestrial samples, and seawater, marine sediment, fish, and seaweed for marine samples. Gamma-emitting radionuclides including $^{137}Cs$, $^{90}Sr$, Pu, $^3H$, and $^{14}C$ are evaluated in these samples. Results and Discussion: According to the result of the environmental radioactivity verification surveillance in the vicinity of nuclear power facilities in 2017, the anthropogenic radionuclides were not detected in most of the environmental samples except for the detection of a trace level of $^{137}Cs$, $^{90}Sr$, Pu, and $^{131}I$ in some samples. Radioactivity concentration ratios between the anthropogenic radionuclides ($^{137}Cs/^{90}Sr$, $^{137}Cs/^{239+240}Pu$, $^{90}Sr/^{239+240}Pu$) were similar to those reported in the environmental samples, which were affected by the global fallout of the past nuclear weapon test, and Pu atomic ratios ($^{240}Pu/^{239}Pu$) in the terrestrial sample and marine sample showed significant differences due to the different input pathway and the Pu source. Radioactive iodine ($^{131}I$) was detected at the range of < $5.6-190mBq{\cdot}kg-fresh^{-1}$ in the gulfweed and sea trumpet collected from the area of Kori and Wolsong intake and discharge. A high level of $^3H$ was observed in the air (Sangbong: $0.688{\pm}0.841Bq{\cdot}m^{-3}$) and the precipitation (Meteorology Post: $199{\pm}126Bq{\cdot}L^{-1}$) samples of the Wolsong nuclear power plant (NPP). $^3H$ concentration in the precipitation and pine needle samples showed typical variation pattern with the distance and the wind direction from the stack due to the gaseous release of $^3H$ in Wolsong NPP. Conclusion: Except for the detection of a trace level of $^{137}Cs$, $^{90}Sr$, Pu, and $^{131}I$ in some samples, anthropogenic radionuclides were below MDC in most of the environmental samples. Overall, no unusual radionuclides and abnormal concentration were detected in the 2017's surveillance result for verification. This research will be available in the assessment of environment around nuclear facilities in the event of radioactive material release.

• Biomolecules & Therapeutics
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• v.5 no.3
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• pp.233-238
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• 1997

The distribution and excretion of radioactivity were examined after intraportal administration of sup 166/Ho-chitosan complex at a dose of 1 mcitg (10 mg chitosan/kg) to rats. Whole body macroautoluminographs showed that the radioactivity after an administration was concentrated in liver and perfused primarily to organs including kidney, spleen, and bone marrow, then to muscle and brain. Similar profiles were observed from 2 hr to 168 hr after the administration. The relative percentage of radioactivity in bone and spinal column increased with time, suggesting that free $^{166}$ Ho, released from chitosan complex deposited in the liver, selectively binds to these tissues. $^{166}$ Ho-chitosan complex administered intraportally was excreted less than 4% through urine (2.7$\pm$0.8%) and feces (0.65 $\pm$ 0.4%) up to seven days. These results demonstrate that the radio-activity of $_{166}$ Ho-chitusan complex when administered intraportally, mainly localizes in liver without affec-ting other tissues and organs. Considering the short half life of $^{166}$ Ho and the localization to the liver, $^{166}$ Ho-chitosan complex might be a useful agent in the treatment of hepatic carcinoma.

• Journal of Sensor Science and Technology
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• v.26 no.6
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• pp.427-431
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• 2017

In this study, a foods radioactivity monitoring sensor was developed as a part of basic research for household radioactivity monitoring, and its performance was evaluated using a calibration source. The prototype of the sensor was based on a CsI:Tl scintillator using a crystal light guide and Si photomultiplier. The light guide was introduced to improve gamma-ray detection efficiency. For quantitative evaluation, tests were conducted using $^{134}Cs$ liquid source. In the performance evaluation, It was confirmed that analysis of $^{134}Cs$: 100 Bq/L(kg) was possible. Thus, result of this study is expected to contribute to research in the development of the household foods radioactivity monitoring system.

• Journal of Radiation Protection and Research
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• v.14 no.2
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• pp.37-44
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• 1989

An improved water chemistry technique was studied to reduce radioactivity build-up in reactor coolant system. The technique is convering the current coordinated lithium-boron chemistry regime to the elevated lithium chemistry regime in order to maintain high pH. Correlations between reactor coolant pH and radioactivity build-up were analized by using pH data from domestic PWRs. Consequently, it was founded that high pH chemistry was moer effective for radioactivity build-up reduction than current chemistry regime. This fact had revealed that much portion of reactor coolant corrosion products were nickel ferrite rather than magnetite, and that pH value ranging 7.0-7.4 was appropriate for high-pH chemistry operation.