Molten Salt Reactor Fuel and Coolant

Beneš, O.; Konings, R.J.M.

doi:10.1016/b978-0-12-803581-8.11790-4

Cited by 7 publications

(4 citation statements)

References 73 publications

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“…They can be either refractory oxides, typically U oxides and MOX, which are also used in current generation reactors [106][107][108][109], or other ceramics, such as carbides [110], nitrides [111,112] and silicides [107,113,114], as well as metallic alloys [115]. Other fuel concepts consider ceramic/ceramic or ceramic/metal composites [116], as well as fluid molten salt fuels [117]. Solid fuel may appear in various geometries: rods, plates or pellets.…”

Section: Fuel Materials For Next Generation Nuclear Systemsmentioning

confidence: 99%

“…Finally, in molten salt reactors (MSR) the fuel can be dissolved in the coolant salt, so that fuel and coolant are one single medium. Molten halides (typically fluorides, but also chlorides) are used as carriers of the fissile (U, Pu) or fertile (U or Th) elements [117,130,131]. The fuel synthesis route has thus very little in common with the established solid fuel pellets fabrication.…”

Section: Fuel Materials For Next Generation Nuclear Systemsmentioning

confidence: 99%

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Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Malerba

Mazouzi²,

Bertolus

et al. 2022

Energies

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Nuclear energy is presently the single major low-carbon electricity source in Europe and is overall expected to maintain (perhaps eventually even increase) its current installed power from now to 2045. Long-term operation (LTO) is a reality in essentially all nuclear European countries, even when planning to phase out. New builds are planned. Moreover, several European countries, including non-nuclear or phasing out ones, have interests in next generation nuclear systems. In this framework, materials and material science play a crucial role towards safer, more efficient, more economical and overall more sustainable nuclear energy. This paper proposes a research agenda that combines modern digital technologies with materials science practices to pursue a change of paradigm that promotes innovation, equally serving the different nuclear energy interests and positions throughout Europe. This paper chooses to overview structural and fuel materials used in current generation reactors, as well as their wider spectrum for next generation reactors, summarising the relevant issues. Next, it describes the materials science approaches that are common to any nuclear materials (including classes that are not addressed here, such as concrete, polymers and functional materials), identifying for each of them a research agenda goal. It is concluded that among these goals are the development of structured materials qualification test-beds and materials acceleration platforms (MAPs) for materials that operate under harsh conditions. Another goal is the development of multi-parameter-based approaches for materials health monitoring based on different non-destructive examination and testing (NDE&T) techniques. Hybrid models that suitably combine physics-based and data-driven approaches for materials behaviour prediction can valuably support these developments, together with the creation and population of a centralised, “smart” database for nuclear materials.

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Section: Fuel Materials For Next Generation Nuclear Systemsmentioning

confidence: 99%

Section: Fuel Materials For Next Generation Nuclear Systemsmentioning

confidence: 99%

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Malerba

Mazouzi²,

Bertolus

et al. 2022

Energies

View full text Add to dashboard Cite

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“…This is largely due to the experience gained during the Molten Salt Reactor Experiment (MSRE) carried out between 1965 and 1969 at the Oak Ridge National Laboratory [3], which was the first thorough demonstration of a civilian Molten Salt test Reactor. Recently, the interest in the use of chloride salts is also rising as an appealing alternative for fast neutron spectra reactors [4]. The latter allow in particular operation with fuel at lower temperatures compared to reactors operated on a fluoride fuel salt mixture [5].…”

Section: Introductionmentioning

confidence: 99%

A Promising Fuel for Fast Neutron Spectrum Molten Salt Reactor Nacl-Thcl4-Pucl3

Dumaire¹,

Flores²,

Konings³

et al. 2022

SSRN Journal

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“…The compositions obtained from the LiF-NaF-CaF 2 -LaF 3 system, as well as many other fluoride systems, are investigated in connection with the development of fourth generation nuclear reactors [1]. In this case, LaF 3 serves as a proxy-compound for PuF 3 , since the direct use of PuF 3 would cause enormous experimental difficulties.…”

Section: Introductionmentioning

confidence: 99%

3D computer models of the T-x-y diagrams, forming the LiF-NaF-CaF2-LaF3 T-x-y-z diagram

Воробьева¹,

Zelenaya²,

Луцык³

et al. 2020

Nanosystems: Phys. Chem. Math.

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Giving professor P. P. Fedorov his due as the leading specialist in fluoride systems and using his theoretical investigations on the topology and geometry of phase diagrams of binary and ternary fluoride systems, as well as experimental results, obtained by colleagues under his leadership, the total geometric description of the systems, forming the LiF-NaF-CaF 2 -LaF 3 system, which has considerable promise for the development of fourth generation fuels for nuclear reactors, has been received. For this purpose, three-dimensional computer models of all four ternary systems have been constructed and the T-x-y-z diagram of this fluoride system has been predicted.

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Molten Salt Reactor Fuel and Coolant

Cited by 7 publications

References 73 publications

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

A Promising Fuel for Fast Neutron Spectrum Molten Salt Reactor Nacl-Thcl4-Pucl3

3D computer models of the T-x-y diagrams, forming the LiF-NaF-CaF2-LaF3 T-x-y-z diagram

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