• The Korean Journal of Nuclear Medicine Technology
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• v.15 no.1
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• pp.70-74
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• 2011

Purpose: In the Nuclear Medicine department of Asan Medical Center, radioactive waste has been disposed of by using several disposal boxes designed for nuclear waste. However, some quantity of radioactivity has been detected occasionally due to some radiologists' carelessness not only from radioactive waste, but also from medical waste such as uncontrolled radioactive waste related to patients, poly gloves or saline solution bottles from radiopharmaceuticals laboratory. Thus, this study is going to suggest a solution to maintain the medical wastes made from controlled areas that can be below maximum permissible surface dose limits by finding the cause of radioactive contamination. Materials and methods: This study was taken place in 17 different places-2 medical wastebaskets in the waiting room, 2 medical wastebaskets in the PET room, 5 medical wastebaskets in the in vitro laboratory and 6 medical wastebaskets in the radiopharmaceuticals laboratory of the East building, 2 medical wastebaskets in the waiting room of the New building of Nuclear Medicine Department in Asan Medical Center from April to August 2010. Mean radioactivity and its standard deviation of each place have been found by measuring surface contamination of medical wastebaskets and backgrounds twice a week, totaling 30 times. An independent t-test of SPSS (Ver. 12.0) statistic program has been used for statistical analysis. Swabs, saline solution bottles and poly gloves collected from each place also measured 30 times, respectively. Results: This study analyzed medical waste and the backgrounds of each place by using survey meter detectors that significant differences of five places did not exist, but existed statistically in twelve places (p<0.05). Also, swabs, saline solution bottles and poly gloves collected from each radioactive waste partly exceed the legal dose limit as a result of measuring by a gamma counter. Conclusion: Backgrounds and the surface doses of radioactive disposal box in all 17 places measured by the survey meter did not exceed the legal dose limit; however, it obviously showed that there were prominent differences in 12 places. Assuming that the cause of the differences was swabs, saline solution bottles and gloves, we examined them by gamma counter, and the results showed remarkably high doses of radioactivity. Consequently, swabs and poly gloves which are normally disposed in the general medical waste box should be disposed in the radioactive waste box furnished by radiopharmaceuticals laboratory. Also, saline solution discharged from radioactive pharmaceutical places is considered as radioactive liquid waste so that it should be disposed of by the septic tank specifically designed for radioactive liquid.

• Nuclear industry
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• v.37 no.2
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• pp.2-19
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• 2017

정부는 1월 25일 국무조정실, 미래창조과학부, 외교부, 산업통상자원부 등 관계부처 합동으로 향후 5년간(2017~21년)의 원자력 진흥 이용 정책 방향을 제시하는 '제5차 원자력진흥종합계획'을 확정했다. 이번 제5차 원자력진흥종합계획 주요 특징은 국민적 관심사인 원전 안전과 방사성폐기물 관리에 역점을 두고 수립됐으며, 갈수록 중요성이 증대되고 있는 소통을 위한 정책이 비중있게 다뤘다는 점이다. 또한 핵심 주제 도출, 추진 전략 설정 등 수립 과정상 온라인 및 오프라인 공청회를 병행하는 등 다양한 의견 수렴 절차를 거쳤으며, 관계 부처 간 유기적인 역할 분담 및 협력 내용을 충실히 반영하고, 원자력 연구개발 5개년 계획을 수립하여 상하위 계획간의 일관성과 실행력을 높였다. 정부는 제5차 원자력진흥종합계획의 충실한 이행을 통해 고준위폐기물 관리 정책 확립 등 투명한 정책 추진으로 국민 신뢰를 향상하고 신기후체제 출범에 따른 온실가스 감축 목표에 효과적으로 대응하며 원자력의 지속적 이용을 통한 국가 성장 동력 창출 기반을 확보할 수 있을 것으로 기대하고 있다. 원자력진흥종합계획은 원자력 진흥 이용 관련 종합 계획으로 지난 1997년부터 매 5년마다 수립하여 추진하고 있다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.491-496
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• 2003

In Korea, the dose limits to the public were reduced according to ICRP-60 recommendations. The secondary quantities, Effluent Concentration Limits (ECLs) were derived and enacted to Korean Atomic Laws based on ICRP-60 recommendations. The Korea atomic laws require assurance that radioactive materials within gaseous effluents do not exceed dose limits and ECLs. This simply means that any effluent that would possibly contain radioactivity must be monitored. There are various methods to monitor the radioactivity of effluent monitor to satisfy the dose limits and the ECLs for gaseous effluents. The many factors (safety margin) should be considered in determining of the setpoint of effluent monitor, following these limits. In this study, we studied the determination method of alarm setpoint for gaseous effluent Radiation Monitoring Systems using dose factors considered the main pathway of radionuclides to compare the preceding determination method of alarm setpoint for gaseous effluent RMSs using dose assessment program considered all the practicable pathways of radionuclides.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2014.10a
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• pp.363-364
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• 2014

국내 에너지의 장기적인 수요상황을 볼 때 원자력 발전의 비중이 확대되는 것은 불가피 하므로 환경 친화적인 사용 후 핵연료의 관리 및 고준위 폐기물의 처분방안의 마련은 원자력의 개발만큼이나 중요하다. 이에 본 연구에서는 방사성 폐기물의 효율적인 관리와 저장 및 열제거를 위하여 최적 환기시스템을 적용한 처분장 설계를 목적으로 여러 환기시스템 설계안을 비교 분석하였다. 분석결과, 8가지 중 case 4(병렬회로)와 case 6(혼합 Diagonal 회로)의 환기효율이 우수한 결과를 나타냈으며, 이와 같은 연구를 통해 환경 친화적인 처분장의 건설이 가능할 것이다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.306-315
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• 2004

A Bridge Transported Servo Manipulator (BTSM) for Advanced spent fuel Conditioning Process (ACP) has been developed to overcome the limitation of access that is a drawback of Mechanical master-slave manipulators (MSMs) for the equipment maintenance. Wire-driven mechanisms have been adopted to increase the handling capacity to weight. The main disadvantage of the wire driven mechanism is that if one link is in motion, other links can be affected because wires and links are coupled. In this paper, the relationship between pulleys and links are formiliarized to overcome this drawbacks, Derived equations are proven and analyzed through experiments.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.12 no.4
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• pp.315-334
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• 2014

Wolsong Low- and Intermediate-level radioactive waste (LILW) disposal center has two different types of disposal facilities and interacts with the neighboring Wolsong nuclear power plant. These situations impose a high level of complexity which requires in-depth understanding of phenomena in the safety assessment of the disposal facility. In this context, multidimensional radionuclide transport model and hydraulic performance assessment model should be developed to identify more realistic performance of the complex system and reduce unnecessary conservatism in the conventional performance assessment models developed for the $1^{st}$ stage underground disposal. In addition, the advanced performance assessment model is required to calculate many cases to treat uncertainties or study parameter importance. To fulfill the requirements, this study introduces the development of two-dimensional integrated near-field performance assessment model combining near-field hydraulic performance assessment model and radionuclide transport model for the $2^{nd}$ stage near-surface disposal. The hydraulic and radionuclide transport behaviors were evaluated by PORFLOW and GoldSim. GoldSim radionuclide transport model was verified through benchmark calculations with PORFLOW radionuclide transport model. GoldSim model was shown to be computationally efficient and provided the better understanding of the radionuclide transport behavior than conventional model.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.2 no.3
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• pp.155-164
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• 2004

Advanced spent fuel Conditioning Process(ACP) project which is under development for efficient spent fuel management has finished process feasibility study and is preparing $\alpha$-${\gamma}$ type hot cell construction for process experimentation. Radiation dose evaluation for the radioactive nuclides were preliminarily performed for normal operation and accident case with the basic concept design report, the meteorological data and the recent site specific data. According to the production and release rate of nuclides, dose evaluations for residents around facility were performed. The evaluation result shows a safe margin for regulation limits and SAR(Safety Analysis Report) limit of IMEF(Irradiated Material Examination Facility) where this facility will be constructed.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.13 no.1
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• pp.1-10
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• 2015

In the safety assessment of the geological disposal system of the radioactive wastes, the abnormal scenarios, in which the system is impacted by the abnormal events, need to be considered in addition to the reference scenario. In this study, characterization and prediction of well intrusion as one of the abnormal events which will impact the disposal system were conducted probabilistically and statistically for the safety assessment. The domestic well development data were analyzed, and the prediction methodologies of the well intrusion were suggested with a computation example. From the results, the annual well development rate per unit area in Korea was about 0.8 well/yr/km² in the conservative point of view. Considering the area of the overall disposal system which is about 1.5 km², the annual well development rate within the disposal system could be 1.2 well/yr. That is, it could be expected that more than one well would be installed within the disposal system every year after the institutional management period. From the statistical analysis, the probabilistic distribution of the well depth followed the log-normal distribution with 3.0363 m of mean value and 1.1467 m of standard deviation. This study will be followed by the study about the impacts of the well intrusion on the geological disposal system, and the both studies will contribute to the increased reliability of safety assessment.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.18 no.2
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• pp.157-167
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• 2020

Removing radioactive concrete is crucial in the decommissioning of nuclear power plants. However, this process generates radioactive aerosols, exposing workers to radiation. Although large amounts of radioactive concrete are generated during decommissioning, studies on the internal exposure of workers to radioactive aerosols generated from the cutting of radioactive concrete are very limited. In this study, therefore, we calculate the internal radiation doses of workers exposed to radioactive aerosols during activities such as drilling and cutting of radioactive concrete, using previous research data. The electrical-mobility-equivalent diameter measured in a previous study was converted to aerodynamic diameter using the Newton-Raphson method. Furthermore, the specific activity of each nuclide in radioactive concrete 10 years after nuclear power plants are shut down was calculated using the ORIGEN code. Eventually, we calculated the committed effective dose for each nuclide using the IMBA software. The maximum effective dose of ¹⁵²Eu constituted 83.09% of the total dose; moreover, the five highest-ranked elements (¹⁵²Eu, ¹⁵⁴Eu, ⁶⁰Co, ²³⁹Pu, ⁵⁵Fe) constituted 99.63%. Therefore, we postulate that these major elements could be measured first for rapid radiation exposure management of workers involved in decommissioning of nuclear power plants, even if all radioactive elements in concrete are not considered.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.8 no.4
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• pp.269-277
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• 2010

Various multilateral approaches to the nuclear fuel cycle have been proposed in order to suppress the expansion of sensitive fuel cycle technology. In order to prepare for the future multilaterallization of the nuclear fuel cycle, existing multilateral spent fuel management programs are analyzed. A trial multilateralization of a domestic R&D facility for the back end of the nuclear fuel cycle is proposed and its challenges, possibilities and implementation strategy are discussed.