• 제목/요약/키워드: radioactive metal

검색결과 276건 처리시간 0.034초

LiCl-KCl 용융염에서 Cd-Li 금속을 이용한 U 및 란탄족의 환원반응 (Reductive reaction of U and Lanthanides using Cd-Li metal in LiCl-KCl Molten Salt)

  • 우문식;이병직;김응호;유재형
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2004년도 학술논문집
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    • pp.339-339
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    • 2004
  • 원자로를 이용하여 장수명핵종(long lived nucleus)을 소멸처리하는 과정에서 초우라늄(TRU, transuranium)과 희토류(RE, rare earth) 금속에 포함되어 있는 소량의 핵분열성(fissile) 물질인 우라늄을 제거할 필요가 있다. 본 실험은 LiCl-KCl 용융염계에서 전해제련법(Electrowinning)을 이용하여 용융염욕에 존재하는 우라늄을 제거하기 위하여 필요한 Cd-Li 양전극 물질을 제조하였고, 제조된 금속을 이용하여 우라늄 및 란탄족(Dy, Ce, Y, Nd, Gd) 금속의 환원 특성을 파악하였다.(중략)

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Electrolytic Deposition of Metal Ions Using A Liquid Cadmium Cathode

  • Shim, Joon-Bo;Ahn, Byung-Gil;Kwon, Sang-Woon;Kim, Eung-Ho;Yoo, Jae-Hyung
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2004년도 학술논문집
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    • pp.337-337
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    • 2004
  • As one of researches for the P & T purposes, a basic experiment on the recovery of actinide elements from the mixture with rare earth elements by means of electrorefining using a liquid cadmium cathode in the LiCl-KC1 eutectic melt was carried out. In order to examine the behaviors of electrodeposition of metal ions on a liquid electrode, recovery experiments of rare earth metals resulting from forming electrodeposits were performed by a galvanostatic electrolysis method at various current densities. A cyclic voltammetric technique was applied to determine reduction-oxidation potential of each metal element in the melt and to detect the changes of the multi component melt composition for on-line monitoring. Also, a collaboration study with RIAR was completed to test the preliminary feasibility on a recovery of actinide elements from the mixture with rare earth elements using a liquid cadmium cathode and actinide metals. Experimental results showed that the ratio of actinides to rare earths, 9: 0.5∼1 led to the rare earth content of about 5∼10 wt% in the deposit.

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해체폐기물운반을 위한 IP-2형 금속용기의 낙하시 유한요소해석 (A Structural Analysis by Finite Element Method under the Dropping Condition of Standardized IP-2 Metal Container for Decommissioning Radwaste Transportation)

  • 최규섭;박제호;박지호
    • 한국기계가공학회지
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    • 제14권6호
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    • pp.35-40
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    • 2015
  • An IP-2 type container is used for the transport of low-level radioactive materials. An IP-2 type metal container was modeled and analyzed for the dropping conditions in normal transport conditions required by NSSC Notice 2014-50, "Regulations on the packaging and transport of radioactive materials." Structural analyses were performed by finite element method, and the acceptability was reviewed by comparing the results with technical standards and maximum allowable stresses of each material. Structural members of the container were modeled as 3D solid elements, and the possible dropping directions were considered in these analyses. Results show that maximum stresses, maximum deformed gaps in the cover, and maximum estimated thickness reduction in structural members were well below the allowable limits; thus, the structural integrity of the container was confirmed.

Electrochemical Behavior for a Reduction of Uranium Oxide in a $LiCl-Li_{2}O$ Molten Salt with an Integrated Cathode assembly

  • Park, Sung-Bin;Park, Byung-Heung;Seo, Chung-Seok;Jung, Ki-Jung;Park, Seong-Won
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2005년도 Proceedings of The 6th korea-china joint workshop on nuclear waste management
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    • pp.39-50
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    • 2005
  • Electrolytic reduction of uranium oxide to uranium metal was studied in a $LiCl-Li_{2}O$ molten salt system. The reduction mechanism of the uranium oxide to a uranium metal has been studied by means of a cyclic voltammetry. Effects of the layer thickness of the uranium oxide and the thickness of the MgO on the overpotential of the cathode and the anode were investigated by means of a chronopotentiometry. From the cyclic voltamograms, the decomposition potentials of the metal oxides are the determining factors for the mechanism of the reduction of the uranium oxide in a $LiCl-3\;wt{\%} Li_{2}O$ molten salt and the two mechanisms of the electrolytic reduction were considered with regards to the applied cathode potential. In the chronopotentiograms, the exchange current and the transfer coefficient based on the Tafel behavior were obtained with regard to the layer thickness of the uranium oxide which is loaded into the porous MgO membrane and the thickness of the porous MgO membrane. The maximum allowable currents for the changes of the layer thickness of the uranium oxide and the thickness of the MgO membrane were also obtained from the limiting potential which is the decomposition potential of LiCl.

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Effect of the Slag Former on the Metal Melting and Radionuclides Distribution in an Electric Arc Furnace

  • Song Song-Pyung;Min Byung-Youn;Choi Wang-Kyu;Chung Chong-Hun;Oh Won-zin
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2005년도 추계 학술대회 논문집
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    • pp.32-37
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    • 2005
  • The characteristics of the metal melting and radionuclide distribution of the radioactive has been investigated in a lab-scale arc furnace. The slag former based on the constituents of silica, calcium oxide, aluminum oxide, borate and calcium fluoride additions was used for melting of the stainless and carbon steel. In the melting of the stainless steel, the amount of slag formation increased with an increase of the concentration of the slag former. But the effects of the slag basicity on the amount of stag formation showed a local maximum value of the slag formation with an increase of the basicity index in the melting of the stainless steel as well as in the melting of the carbon steel. With an increase of the amount of slag former addition, the trends of the cobalt distribution into the ingot and the stag depended on the kind of slag former used in the melting of the stainless steel while the effect of the slag basicity on the distribution of the cobalt was not clarified in the melting of carbon steel. Tn the melting of the carbon steel, the strontium was captured at up to $50\%$ into the slag phase. Cesium was completely eliminated from the melt of the stainless steel as well as the carbon steel and distributed to the dust phase.

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경수로 사용후핵연료 건식저장을 위한 진공건조공정 개발 (Development of the Vacuum Drying Process for the PWR Spent Nuclear Fuel Dry Storage)

  • 백창열;조천형
    • 방사성폐기물학회지
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    • 제14권4호
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    • pp.435-443
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    • 2016
  • 본 논문은 국내 원전의 습식저장조에 저장 중인 경수로형 사용후핵연료를 금속겸용용기를 이용해 건식으로 운영하기 위한 운영공정을 개발하는 것이다. 국내 경수로형 원전의 사용후핵연료는 1990년대 초부터 습식으로 소내에서 운반을 한 경험은 많으나 건식으로 운전한 경험은 전혀 없는 실정이다. 이에 따라 금속겸용용기를 운영할 수 있는 세부 운영공정을 개발하였으며 주요 운영공정에서 금속겸용용기의 주요 구성품 및 사용후핵연료의 안전성이 유지됨을 확인하였다. 단기운영공정은 총 21시간 내에 이루어지도록 절차를 수립하였고 단계별로 허용운전 시간(15시간 습식공정, 3시간 배수공정, 그리고 3시간 진공공정)도 제시하였다.

방사성 폐기물 처리를 위한 이온성 액체 활용 (A Review on the Application of Ionic Liquids for the Radioactive Waste Processing)

  • 박병흥
    • 방사성폐기물학회지
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    • 제12권1호
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    • pp.45-57
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    • 2014
  • 이온성 액체 기술에서의 학문적 연구들은 원자력 산업으로 확대되어 왔으며 많은 연구자들에 의해 방사성 물질의 처리에 이온성 액체의 활용이 연구되어 왔다. 다수의 연구들에 의해 사용 후 핵연료에 포함되어 있는 금속 원소들의 분광학적, 전기화학적 거동에 대한 흥미로운 결과들이 보고되었다. TBP(tri-butyl phosphate)를 용해시킨 이온성 액체에서 측정되고 관찰된 금속 이온들의 물성들은 전통적인 수용성 공정에 대한 대안 기술 개발을 유발시켰다. 한편, 수용성 및 비수용성 공정에서의 활용을 위해 이온성 액체에서 금속 이온의 전기화학적 전착이 연구되었다. 본 연구에서는 이온성 액체 연구에서 주목할 만한 내용들을 분류하고 정리하여 핵연료주기에서 이온성 액체의 활용에 대해 고찰하였다.