• Title/Summary/Keyword: 지르코늄 정련

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Effect of AlF3 on Zr Electrorefining Process in Chloride-Fluoride Mixed Salts for the Treatment of Cladding Hull Wastes (폐 피복관 처리를 위한 염소계-불소계 혼합용융염 내 지르코늄 전해정련공정에서 삼불화알루미늄의 효과 연구)

  • Lee, Chang Hwa;Kang, Deok Yoon;Lee, Sung-Jai;Lee, Jong-Hyeon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.17 no.2
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    • pp.127-137
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    • 2019
  • Zr electrorefining is demonstrated herein using Zirlo tubes in a chloride-fluoride mixed molten salt in the presence of $AlF_3$. Cyclic voltammetry reveals a monotonic shift in the onset of metal reduction kinetics towards positive potential and an increase in intensity of the additional peaks associated with Zr-Al alloy formation with increasing $AlF_3$ concentration. Unlike the galvanostatic deposition mode, a radial plate-type Zr growth is evident at the top surface of the salt during Zr electrorefining at a constant potential of -1.2 V. The diameter of the plate-type Zr deposit gradually increases with increasing $AlF_3$ concentration. Scanning electron microscopy-energy-dispersive X-ray spectroscopy (SEM-EDX) and X-ray photoelectron spectroscopy (XPS) analyses for the plate-type Zr deposit show that trace amount of Al is incorporated as Zr-Al alloys with different chemical compositions between the top and bottom surface of the deposit. Addition of $AlF_3$ is effective in lowering the residual salt content in the deposit and in improving the current efficiency for Zr recovery.

Electrorefining Behavior of Zirconium Scrap with Multiple Cathode in Fluoride-Based Molten Salt (불화물계 용융염을 이용한 지르코늄 스크랩의 다중전극 전해정련 거동)

  • Park, Dong Jae;Kim, Seung Hyun;Park, Kyoung Tae;Mun, Jong Han;Lee, Hyuk Hee;Lee, Jong Hyeon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.13 no.1
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    • pp.11-19
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    • 2015
  • The production of nuclear fuel cladding tube is expected to increase with the nuclear power plant expansion. Zirconium(Zr) scrap that is generated during manufacturing is also expected to increase. Zr electrorefining experiment was carried out in the fluoride salt of LiF-KF-ZrF4 using multiple electrode for scale up and improving throughput Zr electrorefiner develop-ment. The Zr reduction peak observed at-0.8 V(vs.Ni). Polarization behavior showed that the amount of applied current increases because of decreasing cell resistance as the number of cathode increases. Experimental results showed the highest recovery rate about 98% at lowest current density of 25.64 mA/cm2 using 6 electrodes. XRD and TG analysis result show that pure Zr was recovered 99.92% and ICP analysis shows that lower impurity content than conventional impurity content of the Anode(97.8%). Electrorefining consumes energy about 7.15 kWh/kg less than 39.7% compared to the Kroll process using 6 electrode width of 20 mm and height of 65 mm. Because of increasing cell efficiency and recovery rate, using multiple cathode is determined as an efficient technique for scale up electrorefining Zr scrap.

Overview of Zirconium Production and Recycling Technology (지르코늄의 제조(製造)와 재활용기술(再活用技術))

  • Park, Kyoung-Tae;Kim, Seung-Hyun;Hong, Soon-Ik;Choi, Mi-Sun;Cho, Nam-Chan;Yoo, Hwan-Jun;Lee, Jong-Hyeon
    • Resources Recycling
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    • v.21 no.5
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    • pp.18-30
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    • 2012
  • Zirconium is one of the most important material used as cladding of fuel rods in nuclear reactors because of its high dimensional stability, good corrosion resistance and especially low neutron-absorbing cross section. However, Hf free nuclear grade Zr sponge is commercially produced by only three countries including USA, France and Russia. So, Zr has been thoroughly managed as a national strategic material in Korea. Most of the zirconium is used for Korean nuclear industry as nuclear fuel cladding materials manufactured from Hf free Zr alloy raw material. Also, there are some other applications such as alloying element and detonator. In this review, zirconium production and recycling technologies have been reviewed and current industrial status was also analyzed. And recent achievements in innovative reduction technologies such as electrolytic reduction process and molten oxide electrolysis were also introduced.

전해정련 공정에서 지르코늄 및 세륨의 고체음극에 대한 전착특성

  • 권상운;강영호;김응호;유재형
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2004.06a
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    • pp.338-338
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    • 2004
  • 건식공정 (pyrochemical process 혹은 pyroprocessing)은장수명핵종의 소멸처리를 위해서는 장수명핵종을 분리한 뒤 연료로 제조하여야 하며, 분리 공정은 습식공정과 건식공정으로 크게 나누어진다. 용융염을 사용하는 습식공정에 비해 2차 방사성폐기물의 발생량이 적고 공정이 간단하고, 핵확산에 대한 저항성이 매우 크다는 장점 때문에 미래의 핵주기 기술로서 주목받고 있다. 소멸처리를 위해서는 사용 후 핵연료 내에 존재하는 장수명 핵종군 원소들을 분리하고 소멸처리용 연료에 적합한 형태의 물리 화학적 형태로 전환시켜야 한다.(중략)

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