• 제목/요약/키워드: Fusion Temperature

검색결과 650건 처리시간 0.029초

국내 무연탄회의 화학조성 및 용융특성에 관한 연구 (A Study of Chemical Properties and Fusibility of Korean Anthracite Coal Ash)

  • 박철우;이시훈;손응권
    • 분석과학
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    • 제5권4호
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    • pp.433-441
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    • 1992
  • 국내의 23개 무연탄을 대상으로 석탄회의 화학분석 및 용융특성분석을 수행하여 석탄회의 화학조성과 용융온도와의 상관성을 고찰하였다. 또한 이들 무연탄을 미분탄 연소의 연료로 사용시 야기될 수 있는 slagging, fouling성을 예측하여 보았다. 국내 무연탄회는 대부분 $SiO_2$$Al_2O_3$를 80% 이상 함유하고 있는 반면 1% 이하의 적은 양의 $Na_2O$를 함유하고 있으며, 또한 비교적 높은 용융온도를 갖는다. 따라서 이 무연탄들을 미분탄 연소의 연료로 사용시 slagging 및 fouling 발생 가능성은 낮을 것으로 예측되었다. 국내 무연탄회의 용융특성은 base/acid ratio와 비교적 높은 상관성을 갖는 것으로 나타났다.

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Research on Powder Metallurgy Technology in Fusion Materials in China

  • Ge, Chang-Chun;Zhou, Zhang-Jian;Du, Juan;Song, Shu-Xiang
    • 한국분말야금학회:학술대회논문집
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    • 한국분말야금학회 2006년도 Extended Abstracts of 2006 POWDER METALLURGY World Congress Part2
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    • pp.896-897
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    • 2006
  • In the viewpoint of engineering, materials problem is a key problem, which determines whether the exploitation of fusion energy will be success. The most important class of fusion materials is plasma-facing materials (PFM). W, as high Z high melting-point metal is one of the most important candidate materials due to its high plasma erosion resistance. Improving the ductility of W and W based alloy, lowering its ductile-brittleness transition temperature for meeting the requirements of fusion application is an important task. In this paper, severalpowder meatllurgy methods of fabricating W and W based materials are being investigated.

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T-history법에 의한 잠열량 측정 정확도의 향상 (Accuracy Improvement for Measurement of Heat of Fusion by T-history Method)

  • 박창현;백종현;강채동;홍희기
    • 설비공학논문집
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    • 제15권8호
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    • pp.652-660
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    • 2003
  • T-history method, measuring heat-of-fusion of phase change material (PCM) in sealed tubes, has the advantages of a simple experimental device and no requirements in sampling process. However, a degree of supercooling used in selecting the range of latent heat release and neglecting sensible heat during the phase change process can cause significant errors in determining the heat of fusion in the original method, which has been improved in order to predict better results by us. In the present study, the modified method was applied to a variety of PCM such as paraffin and lauric acid having very small or no supercooling with a satisfactory precision. Also the selection of inflection point and temperature measurement position was fumed out not to affect the accuracy of heat-of-fusion significantly. As a result, the method can provide an appropriate means to assess a new developed PCM by cycle test even if a very accurate value cannot be obtained.

Synthesis and Structural Properties of YBa2Cu3O7-x Films/ZnO Nanorods on SrTiO3 Substrates

  • Jin, Zhenlan;Park, C.I.;Song, K.J.;Han, S.W.
    • 한국진공학회:학술대회논문집
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    • 한국진공학회 2012년도 제43회 하계 정기 학술대회 초록집
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    • pp.169-169
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    • 2012
  • The high-temperature superconductor YBa2Cu3O7-x (YBCO) have attached attentions because of a high superconducting transition temperature, low surface resistance, high superconducting critical current density (Jc), and superior superconducting capability under magnetic field. Moreover, the Jc of YBCO superconductors can be enhanced by adding impurities to the YBCO films for vortex-pinning. Understanding and controlling pinning centers are key factors to realize high Jc superconductors. We synthesized vertically-aligned ZnO nanorods on SrTiO3 (STO) substrates by catalyst-free metal-organic chemical vapor deposition (MOCVD), and subsequently, deposited YBCO films on the ZnO nanorods/STO templates using pulsed laser deposition (PLD). The various techniques were used to analyze the structural and interfacial properties of the YBCO/ZnO nanorods/STO hybrid structures. SEM, TEM, and XRD measurements demonstrated that YBCO films on ZnO nanorods/STO were well crystallized with the (001) orientation. EXAFS measurements from YBCO/ZnO nanorods/STO at Cu K edge demonstrated that the local structural properties around Cu atoms in YBCO were quite similar to those of YBCO/STO.

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무전극 마이크로웨이브 플라즈마 토치와 응용 (Electrodelss Plasma Torch Powered by Microwave and Its Applications)

  • 홍용철;전형원;노태협;이봉주;엄환섭
    • 한국신재생에너지학회:학술대회논문집
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    • 한국신재생에너지학회 2009년도 춘계학술대회 논문집
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    • pp.889-892
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    • 2009
  • A microwave plasma torch at the atmospheric pressure by making use of magnetrons operated at the 2.45 GHz and used in a home microwave oven has been developed. This electrodeless torch can be used to various areas, including industrial, environmental and military applications. Although the microwave plasma torch has many applications, we in the present work focused on the microwave plasma torch operated in pure steam and several applications, which may be used in future and right now. For example, a high-temperature steam microwave plasma torch may have a potential application of the hydrocarbon fuel reforming at one atmospheric pressure. Moreover, the radicals including hydrogen, oxygen and hydroxide molecules are abundantly available in the steam torch, dramatically enhancing the reaction speed. Also, the microwave plasma torch can be used as a high-temperature, large-volume plasma burner by injecting hydrocarbon fuels in gas, liquid, and solid into the plasma flame. Lastly, we briefly report an underway research, which is remediation of soils contaminated with oils, volatile organic compounds, heavy metals, etc.

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Design and simulation of a blanket module with high efficiency cooling system of tokamak focused on DEMO reactor

  • Sadeghi, H.;Amrollahi, R.;Zare, M.;Fazelpour, S.
    • Nuclear Engineering and Technology
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    • 제52권2호
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    • pp.323-327
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    • 2020
  • In this study, the neutronic calculation to obtain tritium breeding ratio (TBR) in a deuterium-tritium (D-T) fusion power reactor using Monte Carlo MCNPX is done. In addition, by using COMSOL software, an efficient cooling system is designed. In the proposed design, it is adequate to enrich up to 40% 6Li. Total tritium breeding ratio of 1.12 is achieved. The temperature of helium as coolant gas never exceed 687℃. As regards the tolerable temperature of beryllium (650℃), the design of blanket module is done in the way that beryllium temperature never exceed 600℃. The main feature of this design indicates the temperature of helium coolant is higher than other proposed models for blanket module, therefore power of electricity generation will increase.

Commissioning result of the KSTAR in-vessel cryo-pump

  • Chang, Y.B.;Lee, H.J.;Park, Y.M.;Lee, Y.J.;Kwag, S.W.;Song, N.H.;Park, D.S.;Joo, J.J.;Moon, K.M.;Kim, N.W.;Yang, H.L.;Oh, Y.K.
    • 한국초전도ㆍ저온공학회논문지
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    • 제15권4호
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    • pp.53-58
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    • 2013
  • KSTAR in-vessel cryo-pump has been installed in the vacuum vessel top and bottom side with up-down symmetry for the better plasma density control in the D-shape H-mode. The cryogenic helium lines of the in-vessel cryo-pump are located at the vertical positions from the vacuum vessel torus center 2,000 mm. The inductive electrical potential has been optimized to reduce risk of electrical breakdown during plasma disruption. In-vessel cryo-pump consists of three parts of coaxial circular shape components; cryo-panel, thermal shield and particle shield. The cryo-panel is cooled down to below 4.5 K. The cryo-panel and thermal shields were made by Inconel 625 tube for higher mechanical strength. The thermal shields and their cooling tubes were annealed in air environment to improve the thermal radiation emissivity on the surface. Surface of cryo-panel was electro-polished to minimize the thermal radiation heat load. The in-vessel cryo-pump was pre-assembled on a test bed in 180 degree segment base. The leak test was carried out after the thermal shock between room temperature to $LN_2$ one before installing them into vacuum vessel. Two segments were welded together in the vacuum vessel and final leak test was performed after the thermal shock. Commissioning of the in-vessel cryo-pump was carried out using a temporary liquid helium supply system.

핵융합로용 저방사화 철강재료(RAFs)의 크리프 특성평가 (Evaluation on Creep properties of Reduced Activation Ferritic Steel(RAFs) for Nuclear Fusion Reactor)

  • 공유식;윤한기;김동현;박이현;남승훈
    • 한국해양공학회:학술대회논문집
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    • 한국해양공학회 2003년도 추계학술대회 논문집
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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.

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Fe계 합금 분말 소결품(SMF9060)의 마모 특성 연구 (A Study on Tribological Characteristics of Powder Sintered Fe-base Alloy (SMF9060))

  • 김상윤;김대욱;박영민;신동철;김태규
    • 열처리공학회지
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    • 제27권2호
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    • pp.65-71
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    • 2014
  • SMF9060 material is a Fe-based powder sintered alloy that is used for several automobile components such as Synchronize Hub, oil pump and transmission. These components are required excellent wear resistance and durability. In this study, we have performed a dry wear test at the ambient air and Ar gas conditions in the room temperature, and a lubricant wear test at the room temperature and engine oil temperature of $100^{\circ}C$. The amount of wear volume and coefficient friction are measured by a Profilometer and a Ball on disk type wear tester. The wear volume in Ar gas condition was a little higher than that in the ambient air condition. However the wear volume in the lubricant wear condition was much lower than in the dry wear condition. XRD analysis of the debris in Ar gas condition showed that the oxide film was not formed.