Physical properties data compilations relevant to energy storage :

Janz, George J.; Allen, C. B.; Downey, J. R.; Tomkins, Reginald P. T.

doi:10.6028/nbs.nsrds.61p1

Cited by 64 publications

(69 citation statements)

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“…The eutectic KOH -K2CrO4 mixture at 633 K and 7.8% K2CrO4 was previously reported in the literature [24,25], which is comparable with the values obtained theoretically. The calculated eutectic temperature of the Na2CrO4 -NaOH mixture (560K) is significantly lower than the value for the Na2CrO4 -Na2CO3 system (928 K), which was reported in a previous study by Tathavadkar et al [12].…”

Section: Thermodynamic Considerationssupporting

confidence: 80%

Formation of Chromium-Containing Molten Salt Phase during Roasting of Chromite Ore with Sodium and Potassium Hydroxides

Escudero‐Castejon

Sánchez-Segado

Parirenyatwa

et al. 2016

Journal for Manufacturing Science and Production

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Chromium has a wide range of applications including metals and alloys manufacturing, pigments, corrosion resistance coatings and leather tanning. The production of chromium chemicals is based on the oxidative alkali roasting of chromite ores, which leads to the formation of water-soluble alkali chromates. Previous investigations reported that when chromite is roasted with soda-ash, a molten salt containing chromium, which is mainly composed of sodium carbonate and sodium chromate (Na2CO3-Na2CrO4 binary mixture), forms under typical roasting conditions. The physical properties of the liquid phase, which are dependent on the temperature, charge and gangue compositions, play an important role on the oxidation reaction and may limit the chromate recovery by hindering the oxygen transport to the reaction interface.This investigation focuses on the alkali roasting of chromite ore at 1000 o C using NaOH and KOH, followed by water leaching. The influence of the alkali ratio on the chromium extraction yield is analysed, and the results obtained with both hydroxides are compared. Sample characterisation and thermodynamic analysis, including phase diagrams, equilibrium calculations and computation of liquidus curves, are combined with the purpose of studying the formation of the molten salt phase under different roasting conditions and its effect on the final chromium recovery.

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Section: Thermodynamic Considerationssupporting

confidence: 80%

Formation of Chromium-Containing Molten Salt Phase during Roasting of Chromite Ore with Sodium and Potassium Hydroxides

Escudero‐Castejon

Sánchez-Segado

Parirenyatwa

et al. 2016

Journal for Manufacturing Science and Production

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“…At 100°C all the three fluorides are completely adsorbed. But although UF 6 and NpF 6 can be quantitatively desorbed by gaseous fluorine at 400°C, the desorption of PuF 6 is not possible, because the sorption-produced complex of plutonium PuF 4 .3NaF is thermally stable even in fluorine atmosphere. Partial separation of neptunium from uranium is possible only by sorption of NpF 6 on MgF 2 .…”

Section: Fluoride Volatility Methods -Front-end Of Mstr Fuel Cyclementioning

confidence: 99%

“…A certain fluorine surplus is desirable because the reaction is heterogeneous -between gas and solid phases. Fluorination of actinides yields non-volatile trifluorides of Am and Cm and volatile hexafluorides -stable UF 6 with NpF 6 and unstable PuF 6 (sublimation points of which are 56,5 °C for UF 6 , 55,2 °C for NpF 6 and 62,2 °C for PuF 6 ). Soon after their formation, the gaseous fluorides are condensed in a series of condensers arranged in a descending temperature cascade, which allows separating of higher-boiling (RuF 5 ) and lower-boiling components (SeF 6 , TeF 6 ) from the uranium hexafluoride.…”

Section: Fluoride Volatility Methods -Front-end Of Mstr Fuel Cyclementioning

confidence: 99%

“…However the FVM has not yet acquired industrial maturity and is so far studied on the level of semi-industrial technological tests. In the MSTR fuel cycle the purpose of FVM shall be the separation of spent fuel into three parts -purified uranium (in form of UF 6 for the needs of classical and fast reactors), volatile products of fission products fluorination and a part containing the possible uranium residues, plutonium, minor actinides and fission products that are not forming volatile fluorides. The last part is an input material for the processes of electroseparation and preparation of fresh fuel for the MSTR, where it is separated into three streams again (see Fig.1).…”

Section: Fluoride Volatility Methods -Front-end Of Mstr Fuel Cyclementioning

confidence: 99%

“…The final purification of UF 6 from MoF 6 , TcF 6 , IF 5 and SbF 5 can be performed by fluoride distillation. The distillation of UF 6 is usually performed in the temperature region of 75 to 90°C at pressure between 200 -300 kPa, where the UF 6 forms a liquid phase essential for the distillation process.…”

Section: Fluoride Volatility Methods -Front-end Of Mstr Fuel Cyclementioning

confidence: 99%

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Development of Pyrochemical Reprocessing of the Spent Nuclear Fuel and Prospects of Closed Fuel Cycle

Tulackova¹,

Chuchvalcova-Bimova²,

Precek³

et al. 2012

Atom Indo.

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DEVELOPMENT OF PYROCHEMICAL REPROCESSING OF THE SPENT NUCLEAR FUEL AND PROSPECTS OF CLOSED FUEL CYCLE.Molten-Salt Reactor (MSR) is a design of an advanced reactor system from the GEN IV family working in thermal or epithermal neutron spectrum and using thorium or transuranium fuel in the form of molten fluorides. It is based on the experience with the development of the molten-salt reactor technology in the Oak-Ridge National Laboratory in the United States. The MSR fuel cycle with integrated reprocessing represents one of the potential ways both for significant decrease of total amount of radioactive wastes for final deposition and for utilization of nuclear energy for electricity and heat production as effectively as possible. There are two pyrochemical reprocessing techniques studied in NRI Rez plc which are considered to be applied both for reprocessing of already existing spent fuel and for preparation and "on-line" reprocessing of MSR fuel: (i) the Fluoride Volatility Method (FVM), which performs chemical conversion of spent thermal oxide fuel components into fluorides and their consequent separation by means of their different volatility, thermal stability and chemical affinity to various sorbents; and (ii) electrochemical separation of the actinides (Ans) and fission products (FP), represented mainly by lanthanides (Lns), from each other by electrolytic deposition method on solid cathode in molten fluoride media.

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Enhancement of Heat Capacity of Molten Salt Eutectics using Inorganic Nanoparticles for Solar Thermal Energy Applications

Shin

Banerjee

2011

Ceramic Engineering and Science Proceedings

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Physical properties data compilations relevant to energy storage :

Cited by 64 publications

References 0 publications

Formation of Chromium-Containing Molten Salt Phase during Roasting of Chromite Ore with Sodium and Potassium Hydroxides

Formation of Chromium-Containing Molten Salt Phase during Roasting of Chromite Ore with Sodium and Potassium Hydroxides

Development of Pyrochemical Reprocessing of the Spent Nuclear Fuel and Prospects of Closed Fuel Cycle

Enhancement of Heat Capacity of Molten Salt Eutectics using Inorganic Nanoparticles for Solar Thermal Energy Applications

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