• 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.

• Journal of Radiation Protection and Research
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• v.23 no.2
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• pp.75-82
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• 1998

Tritium concentration in the atmosphere during HTO exposure was different between two experiments due to different velocity of HTO evaporation. Assimilation rate of the rice plant was considered to be higher than that of Chinese cabbage The uptake of atmospheric HTO into tissue free water tritium(TFWT) was higher in rice plants than in Chinese cabbage. However, organically bound tritium(OBT) concentration is relatively higher in Chinese cabbage than in rice. The specific activity ratio(SAR) increased slowly after HTO exposure and decreased gradually with time. The behaviour of HTO in the soil was affected by the environmental conditions.

• Proceedings of the Korean Vacuum Society Conference
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• 2010.08a
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• pp.324-324
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• 2010

핵융합의 고체형 증식(Helium Cooled Solid Breeder : HCSB) 블랑켓(Blanket Module)은 삼중수소 증식을 위해서 Li4SiO4, Li2TiO3, Li2O 및 Li2ZrO3 등의 페블이 고려되고 있다. 이러한 페블을 제조하기 위해서는 먼저 각각의 분말 제조가 선행되어야 한다. 한국의 Test Blanket Module(TBM)은 Li4SiO4 페블을 개발을 개발하여 사용할 예정이고 옵션으로 Li2TiO3 페블을 개발하는 것으로 되어 있다. Li4SiO4 페블을 개발하기 위해서 먼저 분말합성이 필수적이다. Li4SiO4 분말을 합성에 하기 위해서는 Lithium 금속염과 실리카 졸을 용매 및 폴리머 캐리어로서의 두 가지 기능을 하는 에틸렌글리콜에 첨가한 후 가열하여 완전히 용해시킨 후 혼합 용액을 건조시켜 겔형의 전구체를 제조한다. 이를 하소한 후 결정화시켜 Silicate 분말을 얻는데 이때의 건조, 하소 및 결정화 온도의 조건에 따른 분말의 크기 및 특성이 각각 다르다. 즉, 바인더 물질의 비율과 합성온도에 따라 특성이 약간씩 다른 분말을 얻을 수 있었다. 이렇게 얻어진 Silicate 분말은 지르코니아 볼을 이용하여 약 24 시간 동안 볼 밀링 과정을 통해 입도가 작은 미세한 Silicate 분말로 만들었다. 합성된 분말은 여러 가지 시험 및 분석을 통해서 검증되었으며, 불순물 등은 관찰되지 않았다.

• Journal of radiological science and technology
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• v.44 no.4
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• pp.381-387
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• 2021

In this study, for the measurement of 3H(tritium) radioactivity concentration, a study was conducted on whether the type of cocktail and the material of the vial had an effect on the measurement before liquid scintillation counter measurement on HTO-type samples that had undergone physical and chemical pretreatment. As a result of the study, the efficiency according to the type of cocktail was higher in Ultima Gold LLT than Ultima Flo-AP cocktail with polyethylene (1.49%), glass (5.10%), and teflon (6.58%), respectively. Regarding the effect according to the type of vial, the efficiency and SQP(E) of both Ultima Gold LLT and Ultima Flo-AP showed the highest values in the order of teflon, polyethylene, and glass.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11b
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• pp.577-582
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• 1996

삼중수소수와 수소간의 수소동위원소 교환반응을 수행하였다. 촉매로는 백금/SDB고분자촉매, 백금/활성탄촉매 및 니켈/SiO$_2$-A1$_2$O$_3$촉매를 사용하였다. 촉매층의 높이 및 수소유속이 촉매반응효율에 미치는 영향을 관찰하였다. 수소동위원소 교환반응에는 고분자촉매가 가장 높은 효율을 갖는 것이 확인되었다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.396-400
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• 1997

중수형 발전소에서 삼중수소 제거나 중수분리와 관련된 수소동위원소 교환반응에 이용되는 백금담지 고분자촉매제조시 환원과정 이전의 열처리 조건이 백금분산도에 미치는 영향을 관찰하였다. 고분자 담체(SDBC)에 함침법을 이용하여 백금을 담지시켰으며, 8$0^{\circ}C$의 공기중에서 그리고 15$0^{\circ}C$의 산소흐름하에서 열처리하여 제조한 Pt/SDBC촉매의 열적 안정성을 TGA와 BET 실험결과로부터 확인할 수 있었다. 백금담지량이 커지면 백금분산도가 감소하였으며, 가능한 한 고온의 산소로 열처리하면 고분자촉매의 백금분산도가 향상됨을 수소흡착 실험을 통하여 입증하였다.

• Transactions of the Korean hydrogen and new energy society
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• v.23 no.1
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• pp.56-64
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• 2012

The ITER fuel cycle is designed for DT operation in equimolar ratio. It involves not only a group of fuelling system and torus cryo-pumping system of the exhaust gases through the divertor from the torus in tokamak plant, but also from the exhaust gas processing of the fusion effluent gas mixture connected to the hydrogen isotope separation in cryogenic distillation to the final safe storage & delivery of the hydrogen isotopes in tritium plant. Tritium plant system supplies deuterium and tritium from external sources and treats all tritiated fluids in ITER operation. Every operation and affairs is focused on the tritium inventory accountancy and the confinement. This paper describes the major fuel cycle processes and interfaces in the tritium plant in aspects of upcoming technologies for future hydrogen and/or hydrogen isotope utilization.

• Transactions of the Korean hydrogen and new energy society
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• v.22 no.3
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• pp.372-379
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• 2011

A nuclear fusion fuel cycle plant is composed of various subsystems such as a hydrogen isotope storage and delivery system, a tokamak exhaust processing system, and a hydrogen isotope separation system. Korea shares in the construction of its ITER fuel cycle plant with the EU, Japan, and the US, and is responsible for the development and supply of the storage and delivery system. The authors thus present details on the development status of hydrogen isotope storage technologies for nuclear fusion fuel cycle plants. We have developed various hydride beds of different size. We have realized a hydrogen delivery rate of 12.5 $Pam^3/s$ with a typical 1242g-ZrCo bed.

• Proceedings of the Korean Nuclear Society Conference
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• 2002.10a
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• pp.356.2-356
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• 2002

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.527-532
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• 1998

모의 폐액으로 부터 팔라디움을 회수하여 촉매를 제조하였다. 모의 폐액은 장수명핵종 소멸처리 전환시의 군분리 공정에서 발생하는 8성분 폐액으로 하였다. 팔라디움의 회수율은 99.5% 이상이며, 그 순도는 99% 이상의 고품질의 것이었다 회수된 팔라디움을 사용하여 소수성촉매를 제조하였으며, 이 촉매는 400$m^2$/g 이상의 높은 비표면적을 갖는 것으로 나타났다. 질량비로 10%의 시제품촉매를 제조하여 93%의 삼중수소 교환반응효율을 얻을 수 있었다.