• 제목/요약/키워드: Molten salts

검색결과 96건 처리시간 0.03초

리튬용융염에서 플라즈마 용사된 부분안정화 지르코니아 코팅층의 고온부식 거동 (Hot Corrosion Behavior of Plasma-Sprayed Partially Stabilized Zirconia Coatings in a Lithium Molten Salt)

  • 조수행;홍순석;강대승;박병흥;허진목;이한수
    • 대한금속재료학회지
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    • 제46권10호
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    • pp.646-651
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    • 2008
  • The electrolytic reduction of spent oxide fuel involves the liberation of oxygen in a molten LiCl electrolyte, which results in a chemically aggressive environment that is too corrosive for typical structural materials. It is essential to choose the optimum material for the process equipment handling molten salt. IN713LC is one of the candidate materials proposed for application in electrolytic reduction process. In this study, yttria-stabilized zirconia (YSZ) top coat was applied to a surface of IN713LC with an aluminized metallic bond coat by an optimized plasma spray process, and were investigated the corrosion behavior at $675^{\circ}C$ for 216 hours in the molten salt $LiCl-Li_2O$ under an oxidizing atmosphere. The as-coated and tested specimens were examined by OM, SEM/EDS and XRD, respectively. The bare superalloy reveals obvious weight loss, and the corrosion layer formed on the surface of the bare superalloy was spalled due to the rapid scale growth and thermal stress. The top coatings showed a much better hot-corrosion resistance in the presence of $LiCl-Li_2O$ molten salt when compared to those of the uncoated superalloy and the aluminized bond coatings. These coatings have been found to be beneficial for increasing to the hot-corrosion resistance of the structural materials for handling high temperature lithium molten salts.

LiCl 및 LiCl-${Li_2}O$ 용융염에서 Fe-Ni-Cr 합금의 부식거동 연구 (A Study on the Corrosion Behavior of Fe-Ni-Cr Alloys in Molten Salts of LiCl and LiCl-${Li_2}O$)

  • 조수행;장준선;홍순선;신영준;박현수
    • 한국재료학회지
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    • 제10권7호
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    • pp.471-477
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    • 2000
  • Fe-Ni-Cr 합금의 용융염 부식거동을 $650~850^{\circ}C$ 온도범위에서 조사하였다. 용융염 LiCl에서 Cr을 포함하지 않는 KSA(Kaeri Superalloy)-1 합금은 Fe의 내부산화가 발생하고, Cr을 포함한 KSA-4, Incoloy 800H와 KSA-5는 LiCrO$_2$의 치밀한 보호막이 형성되었다. 혼합용융염 $LiCl-LiO_2$O에서 KSA-1은 Fe의 내부산화, KSA-4는 Cr의 내부산화가 발생하였고, Cr 농도가 높은 Incoloy 800H와 KSA-5는 $LiCrO_2$의 다공성 피 이 형성되었다. 혼합용융염 $LiCl-Li_2$O 에서는 Cr 농도의 증가에 따라 부식속도가 증가하였으며, 부식속도는 시간의존선을 8%Cr 이하의 합금에서는 포물선법칙, 8%Cr 이상의 합금에서는 직선법칙을 나타내었다. 이러한 현상은 Li$_2$O에 의한 보호성 산화물 $Cr_2O_3$의 염기성 용해기구로 설명할 수 있다.

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Electrochemical Behavior of Tm ion and Bi ion in LiCl-KCl Molten Salt

  • Kim, Beom-Kyu;Han, Hwa Jeong;Park, Ji Hye;Kim, Won Ki;Park, Byung Gi
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2017년도 추계학술논문요약집
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    • pp.83-84
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    • 2017
  • This study, electrolytic behavior of Thulium and Tm-Bi ion system was studied. The electrochemical behavior of Tm was studied in $LiCl-KCl-TmCl_3$ molten salts using electrochemical techniques Cyclic Voltammetry on tungsten electrodes at 773K. During the process of CV and SWV, intermetallic compound were observed Bi-Tm. Further study, in order to determine clarity of diffusion coefficient in this experiment, we will compare result of electrochemistry method and we also need to quantitative research.

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Electrochemical extraction of uranium on the gallium and cadmium reactive electrodes in molten salt

  • Valeri Smolenski;Alena Novoselova
    • Nuclear Engineering and Technology
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    • 제56권1호
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    • pp.42-47
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    • 2024
  • The electrochemical extraction of uranium in ternary low melting LiCl-KCl-CsCl eutectic on inert and reactive electrodes via different electrochemical techniques was investigated. It was established that the electrochemical reduction process of U(III) ions on the inert W electrode was irreversible and proceeded in one stage. On reactive liquid Ga and liquid Cd electrodes the reduction of uranium ions took place with the considerable depolarization with the formation of UGa2, UGa3 and UCd11 intermetallic compounds. Thermodynamic characteristics of uranium compounds and alloys were calculated. The conditions for the extraction of uranium from the electrolyte in the form of alloys on both liquid reactive electrodes via potentiostatic electrolysis were found.

LiCl-KCl 용융염 내에서 10 g 규모의 Zircaloy-4 폐 피복관 처리를 위한 전기화학적 용해 연구 (Studies on the Electrochemical Dissolution for the Treatment of 10 g-Scale Zircaloy-4 Cladding Hull Wastes in LiCl-KCl Molten Salts)

  • 이유리;이창화;전민구;강권호
    • 방사성폐기물학회지
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    • 제10권4호
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    • pp.273-280
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    • 2012
  • 전해정련을 이용한 폐 피복관 처리의 타당성을 살펴보기 위하여, $500^{\circ}C$의 LiCl-KCl 용융염 내에서 표면이 산화된 10 g 규모의 Zircaloy-4 피복관 및 순수한 Zircaloy-4 피복관의 전기화학적 거동을 살펴보았다. 산화된 Zircaloy-4 피복관이 담긴 basket을 작업전극으로하여 전압-전류 관계를 측정한 결과, 산화되지 않은 Zircaloy-4 피복관과 비교해 Zr의 산화 peak는 Ag/AgCl 기준 전극 대비, 약 -0.7 V ~ -0.8 V로 유사한 반면, 산화 전류의 크기는 확연하게 감소하는 것으로 나타난다. 이러한 결과는 -0.78 V의 일정전위를 가한 전기화학적 용해 실험에서 살펴본 전류-시간 곡선에서도 유사하게 나타나며, 피복관 조각들의 평균 두께 및 무게 변화로부터 확인할 수 있다. Zircaloy-4 피복관이 산화되었을 경우, 표면의 산화막이 피복관의 전도성에 영향을 주어 basket 내 위치에 따라 전기화학적 용해의 균일성 및 속도를 떨어뜨리는 것으로 나타나지만, 표면의 미세한 결함과 Zr 산화물의 상 특성으로 인해 전기화학적 용해가 진행되는 것으로 판단된다.

임피던스법을 적용한 연료전지의 성능평가 (Analysis on the Fuel Cell Performance by the Impedance Method)

  • 김귀열
    • 한국전기전자재료학회논문지
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    • 제20권10호
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    • pp.918-923
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    • 2007
  • Fuel cell is a modular, high efficient and environmentally energy conversion device, it has become a promising option to replace the conventional fossil fuel based electric power plants. The high temperature fuel cell has conspicuous feature and high potential in being used as an energy converter of various fuel to electricity and heat. Corrosions in molten electrolytes and the electric conductivity across the oxide scale have crucial characteristics. When molten salts are involved, high temperature corrosions become severe. In this sense, corrosions of alloys with molten carbonates have the most severe material problems. Systematic investigation on corrosion behavior of Fe/21Cr/Ti or Al alloy has been done in (62+38)mol% (Li+K)$CO_3$ melt at $650^{\circ}C$ using the electrochemical impedance spectroscopy method. It was found that the corrosion current of these Fe-based alloys decreased with increasing Al or Ti. And Al addition improved the corrosion resistance of this type of specimen and more improvement of corrosion resistance was observed at the specimen added with Al.

SELECTIVE REDUCTION OF ACTIVE METAL CHLORIDES FROM MOLTEN LiCl-KCl USING LITHIUM DRAWDOWN

  • Simpson, Michael F.;Yoo, Tae-Sic;Labrier, Daniel;Lineberry, Michael;Shaltry, Michael;Phongikaroon, Supathorn
    • Nuclear Engineering and Technology
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    • 제44권7호
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    • pp.767-772
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    • 2012
  • In support of optimizing electrorefining technology for treating spent nuclear fuel, lithium drawdown has been investigated for separating actinides from molten salt electrolyte. Drawdown reaction selectivity is a major issue that requires investigation, since the goal is to remove actinides while leaving the fission products and other components in the salt. A series of lithium drawdown tests with surrogate fission product chlorides was run to obtain selectivity data with non-radioactive salts, develop a predictive model, and draw conclusions about the viability of using this process with actinide-loaded salt. Results of tests with CsCl, $LaCl_3$, $CeCl_3$, and $NdCl_3$ are reported here. Equilibrium was typically achieved in less than 10 hours of contact between lithium metal and molten salt under well-stirred conditions. Maintaining low oxygen and water impurity concentrations (<10 ppm) in the atmosphere was observed to be critical to minimize side reactions and maintain stable salt compositions. An equilibrium model has been formulated and fit to the experimental data. Good fits to the data were achieved. Based on analysis and results obtained to date, it is concluded that clean separation between minor actinides and lanthanides will be difficult to achieve using lithium drawdown.

Crystal Phase Changes of Zeolite in Immobilization of Waste LiCI Salt

  • KIM Jeong-Guk;LEE Jae-Hee;Lee Sung-Ho;KIM In-Tae;KIM Joon-Hyung;KIM Eung-Ho
    • 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.176-181
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    • 2005
  • The electrolytic reduction process and the electrorefining process, which are being developed at the Korea Atomic Energy Research Institute (KAERI), are to generate molten waste salts such as LiCI salt and LiCI-KCI eutectic salt, respectively. Our goal in waste salt management is to minimize a total waste generation and fabricate a very low­leaching waste form such as a ceramic waste form. Zeolite has been known to one of the most desirable media to immobilize waste salt, which is water soluble and easily radiolyzed. Zeolite can be also used to the removal of fission products from the spent waste salt. Molten LiCI salt is mixed with zeolite A at $650^{\circ}C$ to form a salt-loaded zeolite, and then thermally treated in above $900^{\circ}C$ to become an immobilized product with crystal phase of $Li_{8}Cl_{2}$-Sodalite. In this work, a crystal phase changes of immobilization medium, zeolite, during immobilization of molten LiCI salt using zeolite A is introduced.

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Heat transfer and flow characteristics of a cooling thimble in a molten salt reactor residual heat removal system

  • Yang, Zonghao;Meng, Zhaoming;Yan, Changqi;Chen, Kailun
    • Nuclear Engineering and Technology
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    • 제49권8호
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    • pp.1617-1628
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    • 2017
  • In the passive residual heat removal system of a molten salt reactor, one of the residual heat removal methods is to use the thimble-type heat transfer elements of the drain salt tank to remove the residual heat of fuel salts. An experimental loop is designed and built with a single heat transfer element to analyze the heat transfer and flow characteristics. In this research, the influence of the size of a three-layer thimble-type heat transfer element on the heat transfer rate is analyzed. Two methods are used to obtain the heat transfer rate, and a difference of results between methods is approximately 5%. The gas gap width between the thimble and the bayonet has a large effect on the heat transfer rate. As the gas gap width increases from 1.0 mm to 11.0 mm, the heat transfer rate decreases from 5.2 kW to 1.6 kW. In addition, a natural circulation startup process is described in this paper. Finally, flashing natural circulation instability has been observed in this thimble-type heat transfer element.

Surface modified ceramic fiber separators for thermal batteries

  • Cheong, Hae-Won;Ha, Sang-Hyeon;Choi, Yu-Song
    • Journal of Ceramic Processing Research
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    • 제13권spc2호
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    • pp.308-311
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    • 2012
  • A wide range of possible hazards existing in thermal batteries are mainly caused by thermal runaway, which results in overheating or explosion in extreme case. Battery separators ensure the separation between two electrodes and the retention of ion-conductive electrolytes. Thermal runaways in thermal batteries can be significantly reduced by the adoption of these separators. The high operating temperature and the violent reactivity in thermal batteries, however, have limited the introduction of conventional separators. As a substitute for separators, MgO powders have been mostly used as a binder to hold molten salt electrolyte. During recent decades the fabrication technology of ceramic fiber, which has excellent mechanical strength and chemical stability, has undergone significant improvement. In this study we adopted wet-laid nonwoven paper making method instead of the electrospinning method which is costly and troublesome to produce in volume. Polymeric precursor can readily be coated on the surface of wet-laid ceramic paper, and be formed into ceramic film after heat treatment. The mechanical strength and the thermo-chemical stability as well as the wetting behaviors of ceramic separators with various molten salts were investigated to be applicable to thermal batteries. Due to their excellent chemical, mechanical, and electrical properties, wet-laid nonwoven separators made from ceramic fibers have revealed positive possibility as new separators for thermal batteries which operate at high temperature with no conspicuous sign of a short circuit and corrosion.