The molten salt reactor (MSR) in generation IV: overview and perspectives

Comprehensive Nuclear Materials

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Non-toxic antifouling strategies

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Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects

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Experience with the Molten-Salt Reactor Experiment

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Molten salt reactors: A new beginning for an old idea

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The Molten Salt Reactor Adventure

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Molten-Salt Reactors—History, Status, and Potential

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The thorium molten salt reactor: Moving on from the MSBR

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Molten fluorides for nuclear applications

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Reactor physic and reprocessing scheme for innovative molten salt reactor system

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Towards the thorium fuel cycle with molten salt fast reactors

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Molten Salts Chemistry: From Lab to Applications

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Thermodynamic properties and phase diagrams of fluoride salts for nuclear applications

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The Aircraft Reactor Experiment—Design and Construction

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A road map for the realization of global-scale thorium breeding fuel cycle by single molten-fluoride flow

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Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis

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Molten salt actinide recycler and transforming system without and with Th–U support: Fuel cycle flexibility and key material properties

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Possible Configurations for the Thorium Molten Salt Reactor and Advantages of the Fast Nonmoderated Version

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Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches

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The advanced high-temperature reactor: High-temperature fuel, liquid salt coolant, liquid-metal-reactor plant

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Modelling and analysis of the MSFR transient behaviour

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Molten-salt reactors: new possibilities, problems and solutions

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An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor

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Investigation of the MSFR core physics and fuel cycle characteristics

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Experience with the Molten-Salt Reactor Experiment

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Liquid Fluoride Thorium Reactors

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Alloys compatibility in molten salt fluorides: Kurchatov Institute related experience

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Fluoride Salt-Cooled High-Temperature Reactor Technology Development and Demonstration Roadmap

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Molten Salt Reactor Fuel and Coolant

Beneš, O., & Konings, R. J. M. (2012) · Elsevier eBooks · doi:10.1016/b978-0-08-056033-5.00062-8 · Cited by 66 · see citing works

First elevated-temperature performance testing of coated particle fuel compacts from the AGR-1 irradiation experiment

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Design-Related Studies for the Preliminary Safety Assessment of the Molten Salt Fast Reactor

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AHTR Mechanical, Structural, and Neutronic Preconceptual Design

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Liquid Salt Applications and Molten Salt Reactors

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The AMSTER concept (actinides molten salt transmutER)

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An experimental test facility to support development of the fluoride-salt-cooled high-temperature reactor

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Salts purification and voltammetric study of the electroreduction of U(IV) to U(III) in molten LiF–ThF4

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AHTR Mechanical, Structural, And Neutronic Preconceptual Design

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Coupled study of the Molten Salt Fast Reactor core physics and its associated reprocessing unit

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Preliminary safety calculations to improve the design of Molten Salt Fast Reactor

Brovchenko, M., Heuer, D., Merle, E., et al. (2012) · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · Cited by 25 · see citing works

ENGINEERING DEVELOPMENT STUDIES FOR MOLTEN-SALT BREEDER REACTOR PROCESSING NO. 5.

Oak Ridge National Lab., T. T. U., & McNeese, L. E. (1971) · doi:10.2172/4715383 · Cited by 17 · see citing works

Possible routes for pyrochemical separation: Focus on the reductive extraction in fluoride media

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Evaluation of the Molten Salt Breeder Reactor

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A Preliminary Study of the MSFR Dynamics

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Proceedings of the International Symposium on Environmental monitoring and dose estimation of residents after accident of TEPCO's Fukushima Daiichi Nuclear Power Stations : Shiran Hall, Kyoto, Japan, December 14, 2012

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Nuclear Energy Based on Thorium Molten Salt

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Technical Readiness and Gaps Analysis of Commercial Optical Materials and Measurement Systems for Advanced Small Modular Reactors

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Études préliminaires de sûreté du réacteur à sels fondus MSFR.

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Equilibrium distribution of lanthanum, neodymium, and thorium between fluoride salt melts and liquid bismuth

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Development of pyro-processing technology for thorium-fuelled molten salt reactor

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ENGINEERING DEVELOPMENT STUDIES FOR MOLTEN-SALT BREEDER REACTOR PROCESSING NO. 2.

Oak Ridge National Lab., T. T. U., & McNeese, L. E. (1971) · doi:10.2172/4055059 · Cited by 2 · see citing works

ENGINEERING DEVELOPMENT STUDIES FOR MOLTEN-SALT BREEDER REACTOR PROCESSING NO. 8.

Oak Ridge National Lab., T. T. U., & McNeese, L. E. (1972) · doi:10.2172/4672893 · Cited by 2 · see citing works

Technologies and perspectives for achieving carbon neutrality

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Oxygen-accelerated corrosion of Alloy 800 in a molten LiCl-KCl-MgCl2 eutectic mixture

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Chemistry and technology of Molten Salt Reactors – history and perspectives

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Development of Electrochemical Separation Methods in Molten LiF-NaF-KF for the Molten Salt Reactor Fuel Cycle

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Development of Electrochemical Separation Methods in Molten LiF-NaF-KF for the Molten Salt Reactor Fuel Cycle

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Transmutation: reducing the storage time of spent fuel

Mazgaj, P., & Darnowski, P. (2015) · Journal of Power Technologies

Current Czech R&D in Thorium Molten Salt Reactor (MSR) Technology and Future Directions

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