• Title/Summary/Keyword: 알루미늄 폐기물

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Development on Glass Formulation for Aluminum Metal and Glass Fiber (유리섬유 및 알루미늄 금속 혼합물 유리조성 개발)

  • Cho, Hyun-Je;Kim, Cheon-Woo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.10 no.4
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    • pp.247-254
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    • 2012
  • Vitrification technology has been widely applied as one of effective processing methods for wastes generated in nuclear power plants. The advantage of vitrifying for low- and intermediate-level radioactive wastes has a large volume reduction and good durability for the final products. Recently, a filter using on HVAC(Heating Ventilating & Air Conditioning System) is composed with media (glass fiber) and separator (aluminum film) has been studied the proper treatment technology for meeting the waste disposal requirement. Present paper is a feasibility study for the filter vitrification that developing of the glass compositions for filter melting and melting test for physicochemical characteristic evaluation. The aluminum metal of film type is preparing with 0.5 cm size for proper mixing with glass frit, glass fiber is also preparing with 1 cm size within crucible. The glass compositions should be developed considering molten glass are related with wastes reduction. Glass compositions obtained from developing on glass formulation are mainly composed of $SiO_2$ and $B_2O_3$ for aluminum metal. A variety of factors obtained from the glass formulation and melting test are reviewed, which is feeding rate and glass characteristics of final products such as durability for implementing the wastes disposal requirement.

Melting Characteristics for Radioactive Aluminum Wastes in Electric Arc Furnace (아크 용융로에서 방사성 알루미늄 폐기물의 용융특성)

  • Min, Byung-Youn;Song, Pyung-Seob;Ahn, Jun-Hyung;Choi, Wang-Kyu;Jung, Chong-Hun;Oh, Won-Zin;Kang, Yong
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.4 no.1
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    • pp.33-40
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    • 2006
  • The characteristics of the aluminum waste melting and the distribution of the radioactive nuclides have been investigated for the estimation on the volume reduction and the decontamination of the aluminum wastes from the decommissioning of the TRIGA MARK it and III research reactors at the Korea Atomic Energy Research Institute(KAERI). The aluminum wastes were melted with the use of the fluxes such as flux $A:NaCl-KCl-Na_3AlF_6$, flux B:NaCl-NaF-KF, flux $C:CaF_2$, and flux $D:LiF-KCl-BaCl_2$ in the DC graphite arc furnace. For the assessment of the distribution of the radioactive nuclides during the melting of the aluminum, the aluminum materials were contaminated by the surrogate nuclides such as cobalt(Co), cesium(Cs) and strontium(Sr). The fluidity of aluminum melt was increased with the addition of the fluxes, which has slight difference according to the type of fluxes. The formation of the slag during the aluminum melting added the flux type C and D was larger than that with the flux A and B. The rate of the slag formation linearly increased with increasing the flux concentration. The results of the XRD analysis showed that the surrogate nuclide was transferred to the slag, which can be easily separated from the melt and then they combined with aluminum oxide to form a more stable compound. The distribution ratio of cobalt in ingot to that in slag was more than 40% at all types of fluxes. Since vapor pressures of cesium and strontium were higher than those that of the host metals at the melting temperature, their removal efficiency from the ingot phase to the slag and the dust phase was by up to 98%.

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이온빔 보조에 의한 Al 표면의 에칭 및 산화막 형성

  • 김종민;권봉준;이주선;김명원;김무근;오성근
    • Proceedings of the Korean Vacuum Society Conference
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    • 2000.02a
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    • pp.133-133
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    • 2000
  • 알루미늄 산화막은 알루미늄 전해 커패시터의 유전재료로 많이 사용되고 잇다. 기존의 생산 공정은 양극 산화법에 의한 산화막 형성으로 대부분이 이러한 습식 공정으로 생산되고 있다. 이 양극 산화법 방식은 장점도 있으나 폐기물이 많이 발생되는 단점이 있다. 본 연구에서는 폐기물의 발생을 획기적으로 줄일 수 있고 산화막 형성 효율을 높일 수 잇는 방식으로 activated reactive evaporation(ARE)을 도입하였다. 이 방식은 electron-beam에 의해 알루미늄을 증착시킬 때 plasma를 챔버 내에 발생시켜 활성 반응으로 알루미늄 원자가 산소와 반응하여 기판위에 Al2O3가 증착되는 것이다. 이 방식은 기계적 작동이 단순하고 증착이 되는 여러 변수들의 독립적 조절이 가능하므로 증착을 제어하기 쉽기 때문에 바로 산업 현장에서 적용될 수 있을 것으로 전망되어 본 연구에 도입하게 되었다. 기판은 유전용량을 증가시키기 위하여 알루미늄 원박을 에칭하였다. 이것은 기판으로 쓰일 알루미늄의 표면의 표면적을 증가시키기 위한 것으로, 알루미늄 전극의 표면적을 확대시키면 유전용량이 증가된다. 99.4%의 50$\mu\textrm{m}$와 60$\mu\textrm{m}$ 두께의 알루미늄 원박을 Ar 이온빔에 의해 1keV의 에너지로 20mA로 에칭을 하였다. 에칭 조건별로 에칭상태를 조사하였다. 에칭 후 표면 상태는 AFM으로 관찰하였다. 화성 실험은 진공 챔버 내의 진공을 약 10-7 torr까지 내린 후, 5$\times$10-5 torr까지 O2와 Ar을 주입시킨 다음 filament에서 열전자를 방출시키고 1.2 kV의 electrode에 의해 가속시켜 이들 기체들의 플라즈마를 발생시켰다. e-beam에서 증발된 알루미늄과 활성 반응을 이루어 기판에 Al2O3가 형성되었다. 여러 증착 변수들(O2와 Ar의 분압, 가속 전압, bias 전압 등)과 산화막의 상태 등을 XPS(X-ray photoelectron spectroscopy), AFM(Atomic Force Microscopy), XRD(X-Ray Diffraction), EXD로 조사하였다.

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Property of geopolymers with aluminum smelting waste (알루미늄제련 폐기물을 첨가한 지오폴리머의 물성)

  • Kim, Hakmin;Kim, Yootaek
    • Journal of the Korean Crystal Growth and Crystal Technology
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    • v.32 no.4
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    • pp.143-150
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    • 2022
  • Geopolymers were made by mixing IGCC slag and aluminum smelted waste and their properties were compared with those of IGCC slag based geopolymers. When two raw materials were mixed, the highest compressive strength was obtained at 1.78 of Si/Al ratio. Because the change in compressive strength and density was not so sensitive by the change in Si/Al ratio; that is, the permissible range of Si/Al ratio mixing ratio is broad, it was speculated this broad permissible range would be advantageous for commercialization. The Compressive strength of geopolymers including red mud was higher than that of IGCC based ones and the safety was confirmed by TCLP test. Therefore, it was concluded that the making geopolymers by mixing red mud not only enhances the properties of geopolymers but also gives a recyclability as safe construction materials.

Test Run for the Production of Aluminum Hydroxide by Recycling of Waste Aluminum Dross (알루미늄 폐드로스로부터 수산화알루미늄 생산 시운전 결과)

  • Lee Hooin;Park Ryungkyu;Kim Joonsoo
    • Resources Recycling
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    • v.13 no.2
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    • pp.47-53
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    • 2004
  • Waste aluminum dross is a major waste in the aluminum scrap smelters, and some metallic aluminum remains in the waste dross. In the previous study, waste aluminum dross was leached with sodium hydroxide solution to extract the remained aluminum into the solution, and aluminum hydroxide precipitate was recovered from the leached solution. A pilot plant was constructed and tested to demonstrate the developed technology. One thousand tons of waste aluminum dross could be processed, and about five hundred tons of aluminum hydroxide could be produced in the pilot plant. From the test run of the pilot plant, it was confirmed that the developed technology could be employed as a commercial scale and the produced aluminum hydroxide could be used for water treatment agent.

Characteristics of the Decontamination by the Melting of Aluminum Waste (용융에 의한 알루미늄 폐기물의 제염 특성)

  • Song Pyung-Seob;Choi Wang-Kyu;Min Byung-Youn;Kim Hak-I;Jung Chong-Hun;Oh Won-Zin
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.3 no.2
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    • pp.95-104
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    • 2005
  • Effects of the aluminum melting temperature, melting time and a kind of flux agents on the distribution of surrogate nuclide were investigated in the electric furnace at the aluminum melting including surrogate radionuclides(Co, Cs, Sr) in order to establish the fundamental research of the melting technology for the metallic wastes from the decommissioning of the TRIGA research reactor. It was verified that the fluidity of aluminum melt was increased by adding flux agent but it was slightly varied according to the sort of flux agents. The results of the XRD analysis showed that the surrogate nuclides move into the slag phase and then they were combined with aluminum oxide to form more stable compound. The weight of the slag generated from aluminum melting test increased with increasing melting temperature and melting time and the increase rate of the slag depended on the kind of flux agents added in the aluminum waste. The concentration of the cobalt in the ingot phase decreased with increasing reaction temperature but it increased in the slag phase up to 90$\%$according to the experimental conditions. The volatile nuclides such as Cs and Sr considerably transferred from the ingot phase to the slag and dust phase.

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