• Proceedings of the Korea Committee for Ocean Resources and Engineering Conference
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• 2003.10a
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• pp.146-151
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• 2003

Reduced Activation Ferritic/Martenstic (RAFs) are leading candidates for structural materials of D-T fusion reactor. One of The RAFs, JLF-1 (9Cr-2W-V, Ta) has been developed and proved to have good resistance against high-fluency neutrino irradiation and good phase stability. Recently, in order to clarify the strengthening mechanical at high temperature, a new scheme to improve high temperature mechanical properties is desired. Therefore, the creep properties and creep life prediction by Larson-Miller Parameter method for JLF-1 to be used for fusion reactor materials or other high temperature components were presented at the elevated temperatures of $500^{\circ}C$, $550^{\circ}C$, $600^{\circ}C$, $650^{\circ}C$ and $704^{\circ}C$. It was confirmed experimentally and quantitatively that a creep life predictive e벼ation at such various high temperatures was well derived by LMP.

• Proceedings of the KSME Conference
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• 2003.04a
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• pp.13-18
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• 2003

Reduced activation ferritic steel, JLF-1 steel (Fe-9Cr-2W-V-Ta), is one of the promising candidate materials for fusion reactor applications. Fracture toughness ($J_IC$) and tensile tests were carried out at room temperature and elevated temperature ($400^{\circ}C$). Two types of CT specimen were prepared to examine the effect of rolling direction on the fracture toughness of JLF-1 steel. Four types of tensile specimen were also prepared to investigate the property by the rolling direction and welding. The Micro Vickers hardness was measured at various distances of a cross section of the TIG joints of JLF-1 steel according to the heating history of each position. Finally, the fracture surface was observed by scanning electron microscopy (SEM).

• Journal of Ocean Engineering and Technology
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• v.18 no.2
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• pp.58-63
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• 2004

Reduced Activation Ferritic/Martensitic Steels (RAFs) are leading candidntes for structural materials of a D-T fusion reactor. One of the RAFs, JLF-l (9Cr-2W-V, Ta) has been developed and has shown to have good resistance against high-fluency neutrino irradiation and good phase stability. Recently, in order to clarify the strengthening mechanisms at high temperatures, a new scheme to improve high temperature mechanical properties is desired. Therefore, the test technique development of high temperature creep behaviors for this material is very important. In this paper, the creep properties and creep life prediction, using the Larson-Miler parameter method for JLF-l to be used for fusion reactor materials or other high temperature components, are presented at the elevated temperatures of 50$0^{\circ}C$, 55$0^{\circ}C$, $600^{\circ}C$, $650^{\circ}C$ and 704$^{\circ}C$. It was confirmed, experimentally and quantitatively, that a creep life predictive equation, at such various high temperatures, is well derived mr the LMP method.

• 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.

• Economic and Environmental Geology
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• v.50 no.5
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• pp.415-422
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• 2017

This study focuses on the sustainable development and intelligence information society, analyzing the results of science and technology forecasts from Korea and Japan for 2040-2050. Future geological environment and disaster technologies are presented, such as base geology, geophysical geological disaster, weather adjustment, $CO_2$ reduction, environmental disaster, and smart ecocity developments. For the future technologies in energy and resources technology, space resources development and nuclear fusion will be realized by 2040 and 2050. Moreover, new material and resource technologies will be applied to replace existing energy and mineral resources by 2040. Japan has introduced intelligent information viewpoints and presented new technologies.