Investigation of fused salt systems based on thorium fluoride

Emel'yanov, V. S.; Evstyukhin, A.I.

doi:10.1007/bf01480911

Cited by 4 publications

(1 citation statement)

References 2 publications

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“…However, as a whole, the level of investigation of thorium chemistry in such electrolytes is less thorough than uranium or plutonium chemistry. Information about physical and chemical and electrochemical behavior of thorium in molten halogenides of alkali and alkaline-earth metals is to a considerable extent based on the studies implemented during the 1950-ies -1970-ies (Smirnov and Yudina 1959, Smirnov et al 1970, Smirnov et al 1976, Kudyakov et al 1968, Kudyakov et al 1972, Emelyanov and Evstyukhin 1956a, Emelyanov and Evstyukhin 1956b, Vokhmyakov et al 1973, Smirnov et al 1978, Chiotti et al 1975.…”

Section: Prerequisites For Pyroelectrochemics Production Of Thorium Omentioning

confidence: 99%

Conceptual potential of a pyroelectrochemical technology for the thorium engagement in the fast neutron fuel cycle

Naumov¹

2019

NUCET

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The use of thorium in combination with plutonium in nuclear power generation offers a solution to the problem of reducing the accumulation of long-lived transplutonium nuclides. Along with this, the existing uranium fuel cycle (UFC) has such disadvantage as the vulnerability to unauthorized use of nuclear materials. The thorium fuel cycle (TFC) is devoid of these drawbacks. The engagement of thorium in nuclear power is possible provided the availability of an appropriate technology for reprocessing irradiated thorium. A fuel cycle based on thorium oxide may not differ in principle from the already developed pyrochemical fuel cycle involving uranium and plutonium oxides. Thorium oxide is most commonly obtained in compact state by electrolysis of molten salts from thorium-containing electrolytes. The most thorough studies of physical and chemical and electrochemical behavior of thorium in molten haloids of alkali and alkaline-earth metals were conducted in the 1960ies and the 1970ies. Since extensive experimental material has been accumulated by now for justification of the use of pyroelectrochemical and chemical processes for regeneration of fuel in molten salts, then it has also been proposed that technologies for fuel reprocessing in molten chlorides of alkali metals should be applied resulting in a crystalline product that can be used for the fuel element fabrication. Unlike uranium and plutonium, thorium behavior in molten salt environments is less complex. In molten salts, thorium exists predominantly in the form of Th4+, and the mixture of uranium and thorium dioxides with ThO2 content reaching up to 50 % can be obtained by electrolysis of molten salts. Therefore, the existing amount of knowledge about the chemistry of thorium allows regarding the use of pyrochemical processes in production of thorium oxide as highly promising, and the available data on the physical and chemical properties of thorium and its compounds in high-temperature molten salts makes it possible to state that the pyroelectrochemical technology can be potentially used in production and reprocessing of thorium fuel.

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Section: Prerequisites For Pyroelectrochemics Production Of Thorium Omentioning

confidence: 99%

Conceptual potential of a pyroelectrochemical technology for the thorium engagement in the fast neutron fuel cycle

Naumov¹

2019

NUCET

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High-temperature phase equilibria in lithium-, sodium-, and thorium-fluoride mixtures

Thoma

1972

Journal of Inorganic and Nuclear Chemistry

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The evaporation behaviour of ThF4 mixed of FLiNaK melt during low-pressure distillation

Luo

Geng

et al. 2019

Journal of Nuclear Materials

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Investigation of fused salt systems based on thorium fluoride

Cited by 4 publications

References 2 publications

Conceptual potential of a pyroelectrochemical technology for the thorium engagement in the fast neutron fuel cycle

Conceptual potential of a pyroelectrochemical technology for the thorium engagement in the fast neutron fuel cycle

High-temperature phase equilibria in lithium-, sodium-, and thorium-fluoride mixtures

The evaporation behaviour of ThF4 mixed of FLiNaK melt during low-pressure distillation

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