• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.677-682
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• 1998

영광원전주변 해양에서 조사된 환경방사능 조사결과를 토대로 Cs-137과 Sr-90 방사성물질의 해수와 부유물에서 분포특성과 해양생물로의 전이.농축특성을 분석하였다. 방사성물질의 분포특성 분석은 해양에서 방사성물질의 용해성과 부유물에의 흡착성 평가뿐 아니라 방사성물질의 해양확산을 평가하는데 필수적 요소이다. 지금까지는 방사성물질의 해양확산 평가시 완전 용해성으로 가정하여 단순한 해수유동 특성만을 고려하여 평가하였으나, 흡착성 등 물리화학적 거동특성을 평가함으로써 좀더 사실적인 해양확산을 평가할 수 있다. 평가결과 Cs-137과 Sr-90의 분포특성을 나타내는 분배계수가 각각 8.1$\pm$1.4E-4, 7.4$\pm$2.3E-5 로 나타났다. 이는 두 핵종 모두 용해성이 높고 흡착성이 낮음을 보여준다. 그리고 Cs-137과 Sr-90에 비해 상대적으로 흡착성이 높게 나타나고 있다. 또 전이.농축특성 분석결과는 김에서 Cs-137과 Sr-90의 전이.농축계수가 66과 3, 서대와 병어에서는 122.5와 6, 패류에서는 Sr-90의 전이.농축계수가 6으로 나타났다. Sr-90은 전반적으로 전이.농축계수가 낮게 나타나 생물체에유입되더라도 쉽게 배출돼 축적경향이 매우 낮음을 보여준다. 반면 Cs-137은 Sr-90에 비해 상대적으로 농축특성이 높게 나타나고 있다. 향후 이를 토대로 해역의 고유 환경특성에 맞는 방사성물질의 해양중 거동특성을 고려한 해양확산평가 및 해양감시가 이뤄져야할 것이다.

• Journal of the Institute of Electronics and Information Engineers
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• v.51 no.3
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• pp.10-21
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• 2014

In Fukushima accident, when the severe accident such as a natural disaster happens, it is impossible to monitor the plant status due to a extreme environment and station blackout and most I&C systems break downs. Finally, these cause the loss of emergency cooling function and thus results in a hydrogen explosion and radiation leak. In this paper, the emergency response system is introduced that monitors and controls properly when the sever accidents like Fukushima accident happen, And the performance requirements of a wireless communication system used in the emergency respons system is described and the performance of emergency communication system is analyzed using the markov model.

• Journal of radiological science and technology
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• v.38 no.3
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• pp.305-313
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• 2015

After Fukushima Daiichi nuclear disaster in 2011, study and maintenance of monitoring systems have been made at home and abroad. As concerns about radioactive contamination of water have increased in Korea, update of maintenance of managing radioactive materials in water is being made mainly by Ministry of Environment. In this study, we analysed current state of monitoring system modification in Japan, the country directly involved and neighboring country. According to the result, Japan modified the legislations first. Then Ministry of Education, Culture, Sports, Science and Technology (MEXT) provides theoretical background of radiological monitoring. And Ministry of the Environment actually watches state of water pollution in public waters and underground water. Finally related agencies like local government are monitoring current state of radioactive contamination in water environment. By region, local monitoring stations share the investigation of the whole country. Also, additional monitoring is running around nuclear facilities. After Fukushima disaster, monitoring for area near Fukushima is added. Among the reference levels, management target value of drinking water and tap water is 10 Bq/kg, and those of public water and underground water are 1 Bq/L. Measuring intervals varied from every hour to once a year, regularly or irregularly depending on the investigation. The main measuring items are air dose rate, gross ${\alpha}$, gross ${\beta}$, ${\gamma}$ radionuclide, Cs-134, Cs-137, Sr-89, Sr-90, I-131, and so on. In comparison, regulations about general public water in Korea need to be modified, while those about area near nuclear facility and drinking water are organized well. In future, therefore, domestic system would be expected to be modified with making reference to the guidelines like WHO's one. As good case of applying international guideline to domestic environment, Japanese system could be a reference when general standard of radioactivity in public water is made in Korea.

• Journal of Radiation Protection and Research
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• v.36 no.2
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• pp.71-78
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• 2011

Yeong-Gwang N.P.P Private Environment Supervisory Organization analyzed over 3,000 samples including 10 marine and 24 land samples from the year 2,000 to 2009. According to the results of the analysis, artificial nuclides that resulted from the effect of Yeong-Gwang Nuclear Power Plant operations were not detected in most samples. However, from the rain and seawater samples, which were taken from inside the plants such as the intake, the discharge and the observatory, $^3H$ was detected although it was below the regulation level. The $^3H$ concentration detected in the rain taken from the observatory, by the yearly average criterion, was 30.5~40.0 $Bq{\cdot}L^{-1}$, which is around 20 times the $^3H$ concentration detected in the surroundings of the power plants, but it is 0.1% of the regulation level of 40,000 $Bq{\cdot}L^{-1}$. Also, $^3H$ concentration detected in the seawater taken from the intake and the discharge, by the yearly average criterion, was 2.75~17.8$Bq{\cdot}L^{-1}$, which means the concentration detected in the discharge is about 140~280% higher than that detected in the intake except the year 2006. Based on these results, it was determined that, although lower than the regulation level, the $^3H$ in gas and liquid form detected in the rain and seawater sampled from the observatory and the discharge was released into the environment from the power plants. Therefore, regular monitoring and analysis is required on the level of $^3H$ in the observatory and the discharge.