• 제목/요약/키워드: Cu/Ni alloys

검색결과 158건 처리시간 0.023초

구리 합금 부산물에서의 주석과 니켈의 분리 (Separation of Nickel and Tin from copper alloy dross)

  • 이정일;홍창우;류정호
    • 한국결정성장학회지
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    • 제24권5호
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    • pp.224-228
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    • 2014
  • 최근 금속자원 재활용과 환경보호에 대한 기술적 필요성에 의해 구리(Cu)를 주성분으로 하는 동합금으로부터 니켈, 주석 등의 유가금속의 분리/회수에 대한 관심이 높아지고 있다. 본 연구에서는 기존에 발표한 니켈과 주석의 분리연구 결과를 토대로 보다 높은 농도로 분리할 수 있는 공정을 검토하였다. 니켈의 경우 유기용매를 이용하여 동합금에서 니켈을 선택적으로 분리한 후 환원열처리를 통하여 순도 98.0 % 이상의 니켈 금속분말을 성공적으로 제조하였다. 주석의 경우에는 3회의 연속적인 선택적 용해법과 환원열처리를 통하여 주석 분말의 농도를 97.5 % 이상으로 향상시켰다. 제조된 분말의 FE-SEM 및 TEM 분석을 통하여 미세구조 변화여부를 분석하였다.

Seawater ballast tank 환경에서 저합금강의 내식성에 미치는 합금원소의 영향 (Effects of Alloying Elements on Corrosion Resistance of Low Alloyed Steels in a Seawater Ballast Tank Environment)

  • 김동우;김희산
    • 대한금속재료학회지
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    • 제48권6호
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    • pp.523-532
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    • 2010
  • Co-application of organic coating and cathodic protection has not provided enough durability to low-alloyed steels inseawater ballast tank (SBT) environments. An attempt has made to study the effect of alloy elements (Al, Cr, Cu, Mo, Ni, Si, W) on general and localized corrosion resistance of steels as basic research to develop new low-allowed steels resistive to corrosion in SBT environments. For this study, we measured the corrosion rate by the weigh loss method after periodic immersion in synthetic seawater at $60^{\circ}C$, evaluated the localized corrosion resistance by an immersion test in concentrated chloride solution with the critical pH depending on the alloy element (Fe, Cr, Al, Ni), determined the permeability of chloride ion across the rust layer by measuring the membrane potential, and finally, we analyzed the rust layer by EPMA mapping and compared the result with the E-pH diagram calculated in the study. The immersion test of up to 55 days in the synthetic seawater showed that chromium, aluminium, and nickel are beneficial but the other elements are detrimental to corrosion resistance. Among the beneficial elements, chromium and aluminium effectively decreased the corrosion rate of the steels during the initial immersion, while nickel effectively decreased the corrosion rate in a longer than 30-day immersion. The low corrosion rate of Cr- or Al-alloyed steel in the initial period was due to the formation of $Cr_2FeO_4$ or $Al_2FeO_4$, respectively -the predicted oxide in the E-pH diagram- which is known as a more protective oxide than $Fe_3O_4$. The increased corrosion rate of Cr-alloyed steels with alonger than 30-day exposure was due to low localized corrosion resistance, which is explained bythe effect of the alloying element on a critical pH. In the meantime, the low corrosion rate of Ni-alloyed steel with a longer than 30-day exposure wasdue to an Ni enriched layer containing $Fe_2NiO_4$, the predicted oxide in the E-pH diagram. Finally, the measurement of the membrane potential depending on the alloying element showed that a lower permeability of chloride ion does not always result in higher corrosion resistance in seawater.

Application of Gamma Ray Densitometry in Powder Metallurgy

  • Schileper, Georg
    • 한국분말야금학회:학술대회논문집
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    • 한국분말야금학회 2002년도 제3회 최신 분말제품 응용기술 Workshop
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    • pp.25-37
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    • 2002
  • The most important industrial application of gamma radiation in characterizing green compacts is the determination of the density. Examples are given where this method is applied in manufacturing technical components in powder metallurgy. The requirements imposed by modern quality management systems and operation by the workforce in industrial production are described. The accuracy of measurement achieved with this method is demonstrated and a comparison is given with other test methods to measure the density. The advantages and limitations of gamma ray densitometry are outlined. The gamma ray densitometer measures the attenuation of gamma radiation penetrating the test parts (Fig. 1). As the capability of compacts to absorb this type of radiation depends on their density, the attenuation of gamma radiation can serve as a measure of the density. The volume of the part being tested is defined by the size of the aperture screeniing out the radiation. It is a channel with the cross section of the aperture whose length is the height of the test part. The intensity of the radiation identified by the detector is the quantity used to determine the material density. Gamma ray densitometry can equally be performed on green compacts as well as on sintered components. Neither special preparation of test parts nor skilled personnel is required to perform the measurement; neither liquids nor other harmful substances are involved. When parts are exhibiting local density variations, which is normally the case in powder compaction, sectional densities can be determined in different parts of the sample without cutting it into pieces. The test is non-destructive, i.e. the parts can still be used after the measurement and do not have to be scrapped. The measurement is controlled by a special PC based software. All results are available for further processing by in-house quality documentation and supervision of measurements. Tool setting for multi-level components can be much improved by using this test method. When a densitometer is installed on the press shop floor, it can be operated by the tool setter himself. Then he can return to the press and immediately implement the corrections. Transfer of sample parts to the lab for density testing can be eliminated and results for the correction of tool settings are more readily available. This helps to reduce the time required for tool setting and clearly improves the productivity of powder presses. The range of materials where this method can be successfully applied covers almost the entire periodic system of the elements. It reaches from the light elements such as graphite via light metals (AI, Mg, Li, Ti) and their alloys, ceramics ($AI_20_3$, SiC, Si_3N_4, $Zr0_2$, ...), magnetic materials (hard and soft ferrites, AlNiCo, Nd-Fe-B, ...), metals including iron and alloy steels, Cu, Ni and Co based alloys to refractory and heavy metals (W, Mo, ...) as well as hardmetals. The gamma radiation required for the measurement is generated by radioactive sources which are produced by nuclear technology. These nuclear materials are safely encapsulated in stainless steel capsules so that no radioactive material can escape from the protective shielding container. The gamma ray densitometer is subject to the strict regulations for the use of radioactive materials. The radiation shield is so effective that there is no elevation of the natural radiation level outside the instrument. Personal dosimetry by the operating personnel is not required. Even in case of malfunction, loss of power and incorrect operation, the escape of gamma radiation from the instrument is positively prevented.

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$CeO_2$의 상전이에 따른 YBCO 박막의 결정성 및 특성의 변화 (Change of crystallization and properties of YBCO thin film by phase transition of $CeO_2$)

  • 김성민;이상렬
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 1999년도 하계학술대회 논문집 D
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    • pp.1590-1592
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    • 1999
  • We have fabricated good quality superconducting $YBa_2Cu_3O_{7-{\delta}}$ thin films on Hastelloy(Ni-Cr-Mo alloys) with $CeO_2$ buffer layers by in-situ pulsed laser deposition in a multi-target processing chamber. Using one of electrical properties of YBCO superconducting which the resistance approaches to zero dramatically on transition temperature, we have researched to make power transmission line, we have deposited YBCO thin film on flexible metallic substrate. However, it is difficult to make films on flexible metallic substrates due to both interdiffusion problem between metallic substrate and superconducting layer and non-crystallization of YBCO on amorphous substrate. From early research, two ways-using textured metallic substrate and buffer layer-were proposed to overcome theses difficulties. We have chosen $CeO_2$ as a buffer layer which has cubic structure of $5.41{\AA}$ lattice parameter and only 0.2% of lattice mismatch with $3.82{\AA}$ of a-axis lattice parameter of YBCO on (110) direction of $CeO_2$. In order to enhance the crystallization of YBCO films on metallic substrates we deposited $CeO_2$ buffer layers at varying temperature $700^{\circ}C$ to $800^{\circ}C$ and $O_2$ pressure. By X-ray diffraction, we found that each domination of (200) and (111) orientations were strongly relied upon the deposition temperature in $CeO_2$ layer and the change of the domination of orientation affects the crystallization of YBCO upper layer.

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비정질 금속 기판상에 증착된 YBCO 박막의 결정성에 대한 CEO$_2$ 완충막의 효과 (Effect of CeO$_2$ buffer layer on the crystallization of YBCO thin film on Hastelloy substrate)

  • 김성민;이상렬
    • 한국초전도학회:학술대회논문집
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    • 한국초전도학회 1999년도 High Temperature Superconductivity Vol.IX
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    • pp.392-396
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    • 1999
  • Superconducting YBa$_2Cu_3O_{7-{\delta}}$(YBCO) thin films were grown on Hastelloy(Ni-Cr-Mo alloys) with CeO$_2$ buffer layer in-situ by pulsed laser deposition in a multi-target processing chamber. To apply superconducting property on power transmission line, we have deposited YBCO thin film on flexible metallic substrate. However, it is difficult to grow the YBCO films on flexible metallic substrates due to both interdiffusion problem between metallic substrate and superconducting overlayers and non-crystallization of YBCO on amorphous substrate. It is necessary to use a buffer layer to overcome the difficulties. We have chosen CeO$_2$ as a buffer layer which has cubic structure of 5.41 ${\AA}$ lattice parameter and only 0.2% of lattice mismatch with 3.82 ${\AA}$ of a-axis lattice parameter of YBCO on [110] direction of CeO$_2$ In order to enhance the crystallization of YBCO films on metallic substrates, we deposited CeO$_2$ buffer layers with varying temperature and 02 pressure. By XRD, it is observed that dominated film orientation is strongly depending on the deposition temperature of CeO$_2$ layer. The dominated orientation of CeO$_2$ buffer layer is changed from (200) to(111) by increasing the deposition temperature and this transition affects the crystallization of YBCO superconducting film on CeO$_2$ buffered Hastelloy.

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$\textrm{Fe}_{80-x}\textrm{P}_{10}\textrm{C}_{6}\textrm{B}_{4}\textrm{M}_{x}$(M=Transition Metal) 비정질합금의 열적안정성 (Thermal Stability of $\textrm{Fe}_{80-x}\textrm{P}_{10}\textrm{C}_{6}\textrm{B}_{4}\textrm{M}_{x}$(M=Transition Metal) Amorphous Alloys)

  • 국진선;전우용;진영철;김상협
    • 한국재료학회지
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    • 제7권3호
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    • pp.218-223
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    • 1997
  • 과냉각액체구역(${\Delta}T_{x}=T_{x}-T_{g}$)을 갖는 $Fe_{80}P_{10}C_{6}B_{4}$ 조성에 천이금속(Ti, Zr, Hf, V, Nb, Ta, Cr, Mo, W, Mn, Co, Ni, Pd, Pt및 Cu)를 첨가하여 이들 원소가 유리화온도($T_{g}$), 결정화온도($T_{x}$) 및 과냉액체구역 (${\Delta}T_{x}$)에 미치는 영향에 \ulcorner여 조사하였다. $Fe_{80}P_{10}C_{6}B_{4}$ 합금의 ${\Delta}T_{x}$ 값은 27K였으나 이 합금에 Hf, Ta 및 Mo을 각각 4at%첨가하면 그 값이 40k 이상으로 증가하였다. 이같은 ${\Delta}T_{x}$ 값의 증가는 유리화온도($T_{g}$의 상승보다 결정화온도($T_{x}$)의 상승폭이 크기 때문이다. $T_{g}$$T_{x}$는 외각전자밀도(e/a)가 약 7.38에서 7.05로 감소할수록 상승하였다. e/a의 감소는 천이금속과 다른 구성원소(반금속)사이의 상호결합상태를 의미한다. 즉 $T_{g}$$T_{x}$의 상승은 강한 상호결합력에 기인하는 것으로 사료된다.

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근·현대문화재 인력거 재질분석 연구 (Study on Material Characteristic of Modern Cultural Heritage Rickshaw)

  • 김수철;최재완;이지은
    • 보존과학회지
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    • 제32권1호
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    • pp.33-42
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    • 2016
  • 근 현대문화재는 다양한 재질의 재료가 공존하는 특성을 갖고 있다. 문화재를 보존하고 관리함에 있어 근 현대문화재에 대한 재질분석이 미비한 실정이었다. 본 연구에서는 대한민국역사박물관 소장 인력거를 대상으로 각 재질별로 분석을 실시하였다. 금속, 목재, 도료, 섬유 및 가죽에 대해서 P-XRF, 수종분석, 도막층분석, FT-IR, 현미경 관찰을 통해 분석을 실시하였다. 분석결과 금속은 대부분 구리(Cu), 아연(Zn) 합금이 확인되었고 부분적으로 철(Fe)과 니켈(Ni)이 측정되었다. 특히 니켈(Ni) 합금은 근대시기에 와서 사용된 금속으로 인력거에 사용된 금속이 근 현대에 제작된 것으로 유추할 수 있었다. 목재는 참나무속, 대나무류, 편백나무류가 식별되었다. 편백나무류는 일본 자생종으로 목부재의 일부분이 일본에서 제작되었을 것이라고 판단된다. 도막층은 인력거 외부에 5회 이상 도료가 칠해진 것으로 확인되었고 내부에서는 3회 정도 도료가 칠해진 것으로 나타났다. 이는 내부에서 더 간단한 도색작업이 이루어졌을 것으로 판단된다. 섬유 및 가죽 분석결과 면(Cotton)과 양모(Wool)가 사용되었고 가죽은 우피(牛皮)를 이용한 것으로 사료된다. 본 연구 결과를 토대로 근 현대문화재 재질에 대한 기초 자료 및 진정성 있는 보존 연구에 활용될 것이라 기대한다.

폐전기전자기기(廢電氣電子機器) 스크랩으로부터 귀금속(貴金屬) 및 유가금속(有價金屬) 회수(回收)를 위한 건식공정(乾式工程) 기술(技術) 현황(現況) (Current Status on the Pyrometallurgical Process for Recovering Precious and Valuable Metals from Waste Electrical and Electronic Equipment(WEEE) Scrap)

  • 김병수;이재천;정진기
    • 자원리싸이클링
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    • 제18권4호
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    • pp.14-23
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    • 2009
  • 각종 전기전자제품의 제조과정 또는 사용 후 해체 과정에서 배출되는 폐전기전자기기(WEEE) 스크랩으로부터 금, 은, 팔라듐등 귀금속과 구리, 주석, 니켈등 유가금속의 회수는 금속 재활용측면뿐만 아니라 환경 유해물질 저감의 측면에서도 매우 중요하다. 일반적으로 WEEE 스크랩은 여러 종류의 금속과 합금뿐만 아니라 내화 산화물과 플라스틱 성분 등으로 구성된 복합물질이다. WEEE 스크랩에 함유된 귀금속과 유가금속은 가스휘발공정, 건식공정 또는 습식공정으로 회수될 수 있다. 그러나 가스휘발공정과 습식공정은 아직 기초연구단계에 머물고 있는 실정으로, 현재 WEEE 스크랩으로부터 금, 은, 팔라듐 및 구리 등을 회수하기위한 상업적인 플랜트의 대부분은 건식공정으로 이루어지고 있다. 따라서 본 논문에서는 WEEE 스크랩으로부터 귀금속 및 유가금속을 회수하는 건식공정에 대하여 소개하고, 폐동슬래그를 슬래그 형성제로 활용하여 WEEE 스크랩으로부터 귀금속 및 유가금속을 회수하기 위한 규모 확대 실험에 대한 결과를 제시한다.