• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.222-222
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• 2004

가압 중수로형 원자력발전소에서는 중수 중의 중수소와 중성자의 반응에 의하여 수소동위원소인 삼중수소(트리튬)가 불가피하게 생성되는데 발전소의 가동 년수가 증가함에 따라 계통내 중수중의 삼중수소 농도도 증가하게 된다. 따라서 계통내 삼중수소화 중수로부터 삼중수소를 분리하여, 중수는 원자로로 순환하고 분리된 삼중수소는 별도로 저장할 필요가 있다. 이 과정에서 분리$\cdot$농축된 삼중수소는 방사성 물질일 뿐만 아니라 앞으로 핵융합 연구에 매우 중요하게 이용되어야 할 자원이기 때문에 이를 안전하게 저장하기 위한 기술(저장기술)과 경우에 따라 지정된 장소로 운반하기 위한 기술(운반기술)이 필요하다.(중략)

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.247-247
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• 2004

가압 중수로형 원자력발전소에서는 원자로의 감속재 및 냉각재로 사용하는 중수(heavy water)로 인한 삼중수소(tritium)의 생성이 전체 방사선 준위 상승의 가장 중요한 원인이 되고 있다. 따라서 4기의 중수로가 운전 중인 우리나라에서도 월성원자력 발전소에 삼중수소 제거 설비(Tritium Removal Facility)가 건설 중에 있다. 이 시설로부터 99% 이상의 순도인 삼중수소가 회수되며, 회수된 삼중수소는 장기적인 저장을 위하여 안전하게 포장되어야 한다.(중략)

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.539-543
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• 2003

The objective of this to improve the reliability of the safety evaluation code for Wolsong Tritium Removal Facility(WTRF) which is on the development for environmental assessment. To achieve this, tritium concentrations calculated in the Wolsong Units of this study are compared with that of the existing reference. As the result, the tritium concentration in each Wolsong nuclear power plant unit just before operating WTRF is 60.9Ci/kg, 36.3Ci/kg, 30.0Ci/kg, 26.5Ci/kg under the assumption that the WTRF begins operation in 2005, respectively. This result is almost same with that of the existing reference. But the reducing rate of tritium concentration in the moderator is faster than that of the reference result Finally it is expected to drop below 10Ci/kg after WTRF operation. And this result is also similar with that of the existing reference.

• Proceedings of the Korean Vacuum Society Conference
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• 2012.02a
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• pp.511-511
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• 2012

핵 융합로는 고밀도, 고에너지 플라즈마에 지속적으로 노출되며 고열부하 및 중성자, 플라즈마 이온에 의한 물성변화에 대한 다양한 핵 융합로 구축 재질의 실험데이터가 요구된다. 특히 핵 융합 반응의 핵심연료인 삼중수소의 재질별 누설거동 특성은 삼중수소의 블랑켓에서의 증식율, 열 교환기 및 공급과 회수과정에서의 손실율, 저장, 취급 및 차폐 등의 계산에 활용되므로 핵 융합로의 안전성과 경제성 확보 측면에서 매우 중요하다. 따라서 핵 융합로 구축 재질 선정시 삼중수소의 누설거동 특성은 반드시 고려되어야 한다. 본 연구는 삼중수소 누설거동 특성 해석을 위한 기초실험으로, 수소동위원소를 사용하는 누설거동실험 장치를 설계 제작하여 누설 거동실험을 수행하였다. 누설 가스로는 수소를 사용하였고, 시편은 스테인레스 스틸(SUS-304)을 사용하였으며, 시편의 가열온도는 500, 600, 700, $800^{\circ}C$에서 각각 수소누설거동 실험을 실시하였다. 수소에 대한 SUS-304 재질의 permeability, diffusivity, solubility에 대한 실험 결과를 발표하고자 한다.

• Korean Chemical Engineering Research
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• v.50 no.4
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• pp.595-603
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• 2012

International Thermonuclear Experimental Reactor (ITER) will be constructed in 2019 according to the JIA (Joint Implementation Agreement) of 7 countries. The ITER fusion fuel cycle consists of fusion vacuum vessel, tritium plant and fuelling system. The tritium plant provides the functions of storage, delivery, separation, removal and recovery of the deuterium and tritium used as fusion fuels for the ITER. The tritium plant systems supply deuterium and tritium from external sources and treat all tritiated fluids from ITER operation through Storage and Delivery System (SDS), Tokamak Exhaust Processing (TEP), Isotope Separation System (ISS), Water Detritiation System & Atmosphere Detritiation System (WDS & ADS) and Analysis System (ANS). In this paper, the functions and design requirements of the major systems in the tritium plant and the status of R&D are described. Korean party is developing the SDS for ITER tritium plant and partially attaining the WDS technology through the construction and operation experience of the Wolsong Tritium Removal Facility (WTRF). Now it is expected that researchers in other fields such as chemical engineering take part in the development of upcoming technologies for ISS and TEP.

• Transactions of the Korean hydrogen and new energy society
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• v.26 no.2
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• pp.114-119
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• 2015

Nowdays, fossil fuels have been used as an important resource in development of industry. But it is limited and caused climate change such as pollution and global warming. So nuclear fusion research is being issued with tritium to develop eco-friendly and sustainable energy. Republic of Korea is in charge of Storage and Delivery System (SDS) in the International Thermonuclear Experimental Reactor (ITER), weld present in the SDS bottles are easily exposed to the hydrogen embrittlement of special characteristics of the hydrogen in hydrogen atmosphere, When the hydrogen embrittlement is rapidly progresses, the cracking is generated in the weld zone. Due to this cracking, the risk of leakage of tritium into the atmosphere occurs. In this study, hydrogen heat treatment was processed through the Pressure-Composition-Temperature (PCT) device according to the time variation. Also mechanical properties such as rupture strength test, three point bend test and hardness test in accordance with the respective time have been conducted and the fracture was observed by scanning electron microscopy(SEM) after the mechanical properties evaluation.

• Transactions of the Korean hydrogen and new energy society
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• v.24 no.2
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• pp.121-127
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• 2013

Tritium was attracted with high energy source in neutron fusion energy systems. A number of research was performed in tritium storage materials. The Korea was raised storage and delivery systems (SDS) of international thermonuclear experimental reactor (ITER) research. However, bottles of SDS would be important because of stability. The bottles have a welding zone, this zone will be vulnerable to hydrogen embrittlement. This zone have a high thermodynamic energy and heat deterioration. Therefore bottles were studied about hydrogen embrittlement to retain stability. The heat treatment of hydrogen was carried under pressure-composition-temperature (PCT) apparatus because of checking at real time. And then, mechanical properties were evaluated by tensile test and hardness test. In results of this study, hydrogen atmosphere condition is very important by tensile test and kinetics test. The samples were evaluated, that is more weak hydrogen pressure, increasing temperature and time. This results could be useful in SDS bottle designs.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2010.05a
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• pp.125-126
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• 2010

• Transactions of the Korean hydrogen and new energy society
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• v.26 no.2
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• pp.120-126
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• 2015

Recently, the ever-increasing use of fossil fuels for rapid industrial development and population significantly caused an environment pollution and global warming such as climate change. So research and development of sustainable and eco-friendly energy have been performed. Especially the interest in nuclear fusion fuel was significantly increased from the developed countries. The system of fusion energy production was tritium separation, storage and delivery, and purification. Republic of Korea is in charge of Storage and Delivery System (SDS) in the International Thermonuclear Experimental Reactor (ITER). Welding part of the SDS bottles for storing the tritium is known to be susceptible to hydrogen embrittlement. In this study, conducted a study for the relaxation of the stability and hydrogen embrittlement of the weld area. The hydrogen heat treatment was processed through the Pressure-Composition-Temperature (PCT) device according to the time variation. Also mechanical properties such as impact test and hardness test according to using the alkaline cleaning liquid for hydrogen embrittlement relief and the fracture was observed by scanning electron microscopy (SEM) after the mechanical properties evaluation.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2010.05a
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• pp.85-86
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• 2010