Thermodynamic study of the uranium–vanadium system

Berche, Alexandre; Alpettaz, T.; Chatain, S.; Blanc, Christine; Gossé, Stéphane; Guéneau, C.

doi:10.1016/j.jct.2010.10.023

Cited by 8 publications

(6 citation statements)

References 10 publications

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“…The metallographic analyses of the cooled sample show a primary crystallization phase identified as SiU. In [7], the Si 4 U 5 phase could be stabilized by oxygen impurity. The Si 4 U 5 phase is not present (figure 1 b) contrary to previous observations in [9] (figure 1 c).…”

Section: Experimental Measurementsmentioning

confidence: 98%

“…For the Si47-U53 alloy, the measured temperatures are significantly higher than the calculated ones. The only difference comes from the atmosphere of the furnace: argon in [7] and secondary vacuum in this work. The second phase corresponds to Si 2 U 3 .…”

Section: Experimental Measurementsmentioning

confidence: 99%

“…A detailed description of the experimental device is available in [7]. A detailed description of the experimental device is available in [7].…”

Section: Introductionmentioning

confidence: 99%

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Chemical Compatibility at High Temperature between the Carbide Fuel UC or (U,Pu)C and SiC Cladding for the Gas cooled Fast Reactor

et al. 2010

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The chemical compatibility at high temperature between the fuel kernel (U,Pu)C and SiC cladding, the reference materials for the GFR reactor, is studied. For that purpose, a thermodynamic database on the U-Pu-C-Si system was developed with the Calphad method to calculate the phase diagrams. Differential thermal analysis experiments were performed to measure phase transition temperatures in Si-U and C-Si-U systems. According to the calculated isopleth section between the hyperstoichiometric uranium carbide UC 1.02 and SiC, the materials shall not react below 2056 K, the temperature at which a liquid phase shall form. These calculations are in good agreement with two chemical compatibility tests performed at 1873 K and 2073 K between the materials. Calculations were also performed to study the chemical interaction between the mixed carbide (U,Pu)C 1.04 and SiC. The presence of plutonium in the fuel kernel lowers the liquid formation temperature of 167 K.

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Section: Experimental Measurementsmentioning

confidence: 98%

Section: Experimental Measurementsmentioning

confidence: 99%

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Chemical Compatibility at High Temperature between the Carbide Fuel UC or (U,Pu)C and SiC Cladding for the Gas cooled Fast Reactor

et al. 2010

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“…Fuel UO2, MOX+Am,Np,(U,Pu,Zr), (U,Pu)C, (U,Pu)N FPs: Ag, Ba, Cs, I, La, Mo, Nb, Ru, Sr, Te Materials: Concrete, B-C, Fe-Cr-Ni, SiC,Ta, W, V Solutions 144 binaries 30 ternaries [27,33,34,35,36,37,38,39,40,41,42,43] Japan JAEA, CRIEPI…”

Section: Thermo-calcmentioning

confidence: 99%

TAF-ID: An international thermodynamic database for nuclear fuels applications

Guéneau

Dupin

Kjellqvist³

et al. 2021

Calphad

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“…Vanadium is a significant national strategic resource with properties such as high tensile strength, hardness, high melting point, fatigue resistance, and good corrosion resistance to acids and alkalis. Therefore, it can be widely used in the steel industry, car manufacture, aerospace, the electronics industry, the ceramic industry, and the nuclear industry. − Since vanadium occurs in combination with various minerals, it is necessary to pay attention to the separation and purification processes . Ion exchange, chemical precipitation, and solvent extraction have been used to separate and recover vanadium from vanadium-bearing resources.…”

Section: Introductionmentioning

confidence: 99%

Measurement and Modeling of the Solubility of NH₄VO₃ in the Na₂HPO₄–H₂O and (NH₄)₂HPO₄–H₂O Systems

et al. 2015

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The solubilities of ammonium metavanadate (NH 4 VO 3 ) in (NH 4 ) 2 HPO 4 −H 2 O and Na 2 HPO 4 −H 2 O systems were measured in the temperature range from 298.15 to 338.15 K by the isothermal dissolution method. The experimental data indicate that the solubility of NH 4 VO 3 increases with the addition of Na 2 HPO 4 , while it first decreases and then increases with the addition of (NH 4 ) 2 HPO 4 . The common ion effect and chemical equilibrium were used to explain the solubility tendencies. Two models, the Bromley−Zemaitis model and Pitzer model, were selected to correlate the solubilities of NH 4 VO 3 in the above systems. The parameters of the new model referring to four ion−ion pairs and one ion−molecule pair were obtained via the regression of the experimental data, and the results agreed well with the experimental values. The new chemical model was then applied to analyze the main vanadium-bearing species distribution in the systems mentioned above. All of this work will develop the thermodynamics for an industrial application in the precipitation of NH 4 VO 3 .

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Thermodynamic study of the uranium–vanadium system

Cited by 8 publications

References 10 publications

Chemical Compatibility at High Temperature between the Carbide Fuel UC or (U,Pu)C and SiC Cladding for the Gas cooled Fast Reactor

Chemical Compatibility at High Temperature between the Carbide Fuel UC or (U,Pu)C and SiC Cladding for the Gas cooled Fast Reactor

TAF-ID: An international thermodynamic database for nuclear fuels applications

Measurement and Modeling of the Solubility of NH₄VO₃ in the Na₂HPO₄–H₂O and (NH₄)₂HPO₄–H₂O Systems

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Thermodynamic study of the uranium–vanadium system

Cited by 8 publications

References 10 publications

Chemical Compatibility at High Temperature between the Carbide Fuel UC or (U,Pu)C and SiC Cladding for the Gas cooled Fast Reactor

Chemical Compatibility at High Temperature between the Carbide Fuel UC or (U,Pu)C and SiC Cladding for the Gas cooled Fast Reactor

TAF-ID: An international thermodynamic database for nuclear fuels applications

Measurement and Modeling of the Solubility of NH4VO3 in the Na2HPO4–H2O and (NH4)2HPO4–H2O Systems

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Measurement and Modeling of the Solubility of NH₄VO₃ in the Na₂HPO₄–H₂O and (NH₄)₂HPO₄–H₂O Systems