• Title/Summary/Keyword: cesium salt

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Assessment on Recovery of Cesium, Strontium, and Barium From Eutectic LiCl-KCl Salt With Liquid Bismuth System

  • Woods, Michael E.;Phongikaroon, Supathorn
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.18 no.4
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    • pp.421-437
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    • 2020
  • This study provides an assessment on a proposed method for separation of cesium, strontium, and barium using electrochemical reduction at a liquid bismuth cathode in LiCl-KCl eutectic salt, investigated via cyclic voltammetry (CV), electrochemical impedance spectroscopy (EIS), and scanning electron microscopy with energy dispersive X-ray spectrometry (SEM-EDS). CV studies were performed at temperatures of 723-823 K and concentrations of the target species up to 4.0wt%. Redox reactions occurring during potential sweeps were observed. Concentration of BaCl2 in the salt did not seem to influence the diffusivity in the studied concentration range up to 4.0wt%. The presence of strontium in the system affected the redox reaction of lithium; however, there were no distinguishable redox peaks that could be measured. Impedance spectra obtained from EIS methods were used to calculate the exchange current densities of the electroactive active redox couple at the bismuth cathode. Results show the rate-controlling step in deposition to be the mass transport of Cs+ ions from the bulk salt to the cathode surface layer. Results from SEM-EDS suggest that Cs-Bi and Sr-Bi intermetallics from LiCl-KCl salt are not thermodynamically favorable.

Cesium and strontium recovery from LiCl-KCl eutectic salt using electrolysis with liquid cathode

  • Jang, Junhyuk;Lee, Minsoo;Kim, Gha-Young;Jeon, Sang-Chae
    • Nuclear Engineering and Technology
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    • v.54 no.10
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    • pp.3957-3961
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    • 2022
  • Deposition behaviors of Sr and Cs in various liquid cathodes, such as Zn, Bi, Cd, and Pb, were examined to evaluate their recovery from LiCl-KCl eutectic salt. Cations in the salt were deposited on the liquid cathode, exhibiting potential of -1.8 to -2.1 V (vs. Ag/AgCl). Zn cathode had successful deposition of Sr and exhibited the highest recovery efficiency, up to 55%. Meanwhile, the other liquid cathodes showed low current efficiencies, below 18%, indicating LiCl-KCl salt decomposition. Sr was recovered from the Zn cathode as irregular rectangular SrZn13 particles. A negligible amount of Cs was deposited on the entire liquid cathode, indicating that Cs was hardly deposited on liquid cathodes. Based on these results, we propose that liquid Zn cathode can be used for cleaning Sr in LiCl-KCl salt.

SEPARATION OF STRONTIUM AND CESIUM FROM TERNARY AND QUATERNARY LITHIUM CHLORIDE-POTASSIUM CHLORIDE SALTS VIA MELT CRYSTALLIZATION

  • WILLIAMS, AMMON N.;PACK, MICHAEL;PHONGIKAROON, SUPATHORN
    • Nuclear Engineering and Technology
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    • v.47 no.7
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    • pp.867-874
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    • 2015
  • Separation of cesium chloride (CsCl) and strontium chloride ($SrCl_2$) from the lithium chloride-potassium chloride (LiCl-KCl) salt was studied using a melt crystallization process similar to the reverse vertical Bridgeman growth technique. A ternary $SrCl_2-LiCl-KCl$ salt was explored at similar growth rates (1.8-5 mm/h) and compared with CsCl ternary results to identify similarities. Quaternary experiments were also conducted and compared with the ternary cases to identify trends and possible limitations to the separations process. In the ternary case, as much as 68% of the total salt could be recycled per batch process. In the quaternary experiments, separation of Cs and Sr was nearly identical at the slower rates; however, as the growth rate increased, $SrCl_2$ separated more easily than CsCl. The quaternary results show less separation and rate dependence than in both ternary cases. As an estimated result, only 51% of the total salt could be recycled per batch. Furthermore, two models have been explored to further understand the growth process and separation. A comparison of the experimental and modeling results reveals that the nonmixed model fits reasonably well with the ternary and quaternary data sets. A dimensional analysis was performed and a correlation was identified to semipredict the segregation coefficient.

Polymeric Membrane Cesium-Selective Electrodes Based on Quadruply-bridged Calix[6]arenes

  • Choe, Eun Mi;O, Hye Jin;Go, Seung Hwa;Choe, Yong Guk;Nam, Gye Chun;Jeon, Seung Won
    • Bulletin of the Korean Chemical Society
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    • v.22 no.12
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    • pp.1345-1349
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    • 2001
  • New quadruply-bridged calix[6]arenes (I-V) have been studied as cesium selective ionophores in poly(vinyl chloride) (PVC) membrane electrodes. PVC membranes were prepared with dioctyl sebacate (DOS) or 2-nitrophenyl octyl ether (o-NPOE) as the sol vent mediator and potassium tetrakis(p-chlorophenyl)borate as the lipophilic salt additive. These ionophores produced electrodes with near-Nernstian slope. The selectivity coefficients for cesium ion with respect to alkali, alkaline earth and ammonium ions have been determined. The lowest detection limit (logaCs+ = -6.3) and the higher selectivity coefficient (logkpotCs+,Rb+ = -2.1 by SSM, -2.3 by FIM for calix[6]arene I) for Cs+ have been obtained for membranes containing quadruply-bridged calix[6]arenes (I, Ⅱ, Ⅲ), which have no para t-butyl substituents on the bridging benzene ring.

Syntheses and Thermal Behaviors of Rb(FOX-7)·H2O and Cs(FOX-7)·H2O

  • Luo, Jinan;Xu, Kangzhen;Wang, Min;Song, Jirong;Ren, Xiaolei;Chen, Yongshun;Zhao, Fengqi
    • Bulletin of the Korean Chemical Society
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    • v.31 no.10
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    • pp.2867-2872
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    • 2010
  • Two new energetic organic alkali metal salts, 1,1-diamino-2,2-dinitroethylene rubidium salt [Rb(FOX-7)${\cdot}H_2O$] and 1,1-diamino-2,2-dinitroethylene cesium salt [Cs(FOX-7)${\cdot}H_2O$], were synthesized by reacting of 1,1-diamino-2,2-dinitroethylene (FOX-7) and rubidium chloride or cesium chloride in alkali methanol aqueous solution, respectively. The thermal behaviors of Rb(FOX-7)${\cdot}H_2O$ and Cs(FOX-7)${\cdot}H_2O$ were studied with DSC and TG methods. The critical temperatures of thermal explosion of the two compounds are 216.22 and $223.73^{\circ}C$, respectively. Specific heat capacities of the two compounds were determined with a micro-DSC method, and the molar heat capacities are 217.46 and $199.47\;J\;mol^{-1}\;K^{-1}$ at 298.15 K, respectively. The adiabatic times-to-explosion were also calculated to be a certain value of 5.81 - 6.36 s for Rb(FOX-7)${\cdot}H_2O$, and 9.92 - 10.54 s for Cs(FOX-7)${\cdot}H_2O$. After FOX-7 becoming alkali metal salts, thermal decomposition temperatures of the compounds heighten with the rise of element period, but thermal decomposition processes become intense.

A Study on the Process Improvement of RJ-4 fuel Preparation using a Heteropoly Acid Catalyst (Heteropoly acid촉매를 이용한 RJ-4연료의 제조공정 개선연구)

  • Jeong Byung-Hun;Han Jeong-Sik;Choi Chang-Sun;Hong Myung-Pyo
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2005.11a
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    • pp.229-232
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    • 2005
  • The study on the improvement of manufacturing process of RJ-4 liquid fuel that have high flash point, was carried out. In preparing of RJ-4 using commercially available MCPD, 1st, 2nd hydrogenation and isomerization reaction were enabled 1 step continuous process by combined use of heteropoly phosphoroustungstic cesium salt catalyst and 2nd stage-heat-controllable reactor. Also when heteropolyacid cesium salt was used as a isomerization catalyst instead of aluminum chloride, formation rate of exe-THDMCPD was higher, the catalyst could be easily separable from product and there was no production of waste acid, so this new reaction condition was confirmed as the environment friendly process.

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Attachment Behavior of Fission Products to Solution Aerosol

  • Takamiya, Koichi;Tanaka, Toru;Nitta, Shinnosuke;Itosu, Satoshi;Sekimoto, Shun;Oki, Yuichi;Ohtsuki, Tsutomu
    • Journal of Radiation Protection and Research
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    • v.41 no.4
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    • pp.350-353
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    • 2016
  • Background: Various characteristics such as size distribution, chemical component and radio-activity have been analyzed for radioactive aerosols released from Fukushima Daiichi Nuclear Power Plant. Measured results for radioactive aerosols suggest that the potential transport medium for radioactive cesium was non-sea-salt sulfate. This result indicates that cesium isotopes would preferentially attach with sulfate compounds. In the present work the attachment behavior of fission products to aqueous solution aerosols of sodium salts has been studied using a generation system of solution aerosols and spontaneous fission source of $^{248}Cm$. Materials and Methods: Attachment ratios of fission products to the solution aerosols were compared among the aerosols generated by different solutions of sodium salt. Results and Discussion: A significant difference according as a solute of solution aerosols was found in the attachment behavior. Conclusion: The present results suggest the existence of chemical effects in the attachment behavior of fission products to solution aerosols.

Study on the Isomerization Reaction of Tetrahydrodicyclopentadiene, Tetrahydrodi(methylcyclopentadiene) Using Heteropolyacid Catalyst (헤테로폴리산 촉매를 이용한 Tetrahydrodicyclopentadiene 및 Tetrahydrodi(methylcyclopentadiene)의 이성화반응 연구)

  • Jeong, Byung Hun;Han, Jeong Sik;Kim, Seong Bo;Kang, Cheol Han;Lee, Bum Jae
    • Applied Chemistry for Engineering
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    • v.18 no.1
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    • pp.36-40
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    • 2007
  • The study on the isomerization reaction of endo-tetrahydrodicyclopentadiene and endo-tetrahydrodi(methylcyclopentadiene) using heteropolyacid catalyst was carried out. Exo compound was prepared from endo compound through isomerization reaction. To improve the problem of aluminum chloride as an isomerization catalyst, application of heteropolyacid was attempted. In use of Keggin type heteropolyacid, catalytic activity was extremely high at cesium substitution instead of 2.5 hydrogen atoms of $H_3PW_{12}O_{40}$. Using the cesium substituted heteropolyacid, isomerization reaction rate was faster than aluminum chloride and the effect of reaction temperature and times on reactivities were compared in isomerization of tetrahydrodicyclopentadiene and tetrahydrodi(methylcyclopentadiene).

Measurements of Separation Properties of AM, ARM Oxidesin Molten LiC1 (AM, AEM 산화물들의 용융 LiC1에서의 분리 물성 측정)

  • 오승철;박병흥;강대승;서중석;박성원
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.363-367
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    • 2003
  • Much attention has been given to an electrochemical reduction process for converting uranium oxide to uranium metal in molten salt. The process has the versatility of being adopted for reducing other actinide and rare-earth metals from their oxides. Using the metal oxide to be reduced as a integrated cathode designed originally and inert conductors as anodes, oxygen anions are removed from the cathode and oxidized at the surface of the anodes in a molten salt cell. However, the electrochemical properties of alkali and alkali-earth metal oxides in molten salt have not been investigated thoroughly, which made the process incomplete when it is considered as a unit process in a back-end fuel cycle. It is well known that cesium and strontium Isotopes in spent fuel are main contributors for head load. The properties of cesium, strontium, and barium oxides such as the dissolution rates and reduction potentials in molten LiC1 dissolving $Li_2O$ are examined.

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Study of Composite Adsorbent Synthesis and Characterization for the Removal of Cs in the High-salt and High-radioactive Wastewater (고염/고방사성 폐액 내 Cs 제거를 위한 복합 흡착제 합성 및 특성 연구)

  • Kim, Jimin;Lee, Keun-Young;Kim, Kwang-Wook;Lee, Eil-Hee;Chung, Dong-Yong;Moon, Jei-Kwon;Hyun, Jae-Hyuk
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.15 no.1
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    • pp.1-14
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    • 2017
  • For the removal of cesium (Cs) from high radioactive/high salt-laden liquid waste, this study synthesized a highly efficient composite adsorbent (potassium cobalt ferrocyanide (PCFC)-loaded chabazite (CHA)) and evaluated its applicability. The composite adsorbent used CHA, which could accommodate Cs as well as other molecules, as a supporting material and was synthesized by immobilizing the PCFC in the pores of CHA through stepwise impregnation/precipitation with $CoCl_2$ and $K_4Fe(CN)_6$ solutions. When CHA, with average particle size of more than $10{\mu}m$, is used in synthesizing the composite adsorbent, the PCFC particles were immobilized in a stable form. Also, the physical stability of the composite adsorbent was improved by optimizing the washing methodology to increase the purity of the composite adsorbent during the synthesis. The composite adsorbent obtained from the optimal synthesis showed a high adsorption rate of Cs in both fresh water (salt-free condition) and seawater (high-salt condition), and had a relatively high value of distribution coefficient (larger than $10^4mL{\cdot}g^{-1}$) regardless of the salt concentration. Therefore, the composite adsorbent synthesized in this study is an optimized material considering both the high selectivity of PCFC on Cs and the physical stability of CHA. It is proved that this composite adsorbent can remove rapidly Cs contained in high radioactive/high salt-laden liquid waste with high efficiency.