Results 51 to 60 of about 2,437 (261)

A Molten Salt Extraction Method for Palladium Recovery via the CaPd2 Intermetallic Compound

open access: yesAdvanced Science, EarlyView.
A designed Ca → CaPd2 → Pd pathway enables acid–free palladium recovery in molten salt. Calcium alloying forms anionic CaPd2, which is selectively oxidized by iodine from CaI2 to yield high–purity metallic Pd. ABSTRACT To address palladium scarcity and the low efficiency of conventional recovery processes, this work presents a molten–salt extraction ...
Jiapeng Zhang   +6 more
wiley   +1 more source

Understanding Electrochemical Interactions of Iodide and Chloride Species in LiCl-KCl Molten Salt

open access: yesInorganics
Iodine is produced through nuclear fission reactions in nuclear reactors. Understanding the electrochemistry of iodine species is crucial for reprocessing used nuclear fuels via molten salt electrolysis, deploying next-generation molten salt nuclear ...
Nikunja Shrestha   +3 more
doaj   +1 more source

Unveiling Mechanisms of SEI Formation and Sodium Loss in Sodium Batteries via Interface Reactor Sampling

open access: yesAdvanced Science, EarlyView.
An “Interface Reactor” strategy boosts simulation stability by 2–3 orders of magnitude, enabling stable 100 ns molecular dynamics of electrode‐electrolyte interfaces. Distinct SEI formation mechanisms are revealed: mixed co‐formation in carbonates versus surface‐energy‐controlled NaF crystallization in ethers. Metadynamics simulations further elucidate
Zhoulin Liu   +6 more
wiley   +1 more source

Green and Low‐Carbon Synthesis of Lithium Sulfide (Li2S): From Fundamental Mechanisms to Scalable Manufacturing for Next‐Generation Energy Storage

open access: yesAdvanced Science, EarlyView.
This review focuses on green synthesis routes for lithium sulfide (Li2S)—a key material for lithium–sulfur batteries and sulfide solid electrolytes, whose traditional carbothermal reduction remains energy‐intensive and unsustainable. Specifically examined routes include low‐temperature solid‐state reactions, magnesiothermal reduction, and solution ...
Aiping Peng   +11 more
wiley   +1 more source

A PRELIMINARY STUDY OF MOLTEN SALT POWER REACTORS [PDF]

open access: yes, 1957
A preliminary study of molten salt pcwer reactors was made. The most promising fuel carrier salts were the fluorides and chlorides of the alkali metals, zirconium, and beryllium.
Kinyon, B. W.   +8 more
core   +1 more source

Applicability Analysis of Reduced-Order Methods with Proper Orthogonal Decomposition for Neutron Diffusion in Molten Salt Reactor

open access: yesEnergies
The high-dimensional integral–differential nature of the neutron transport equation and the complexity of nuclear reactors result in high computational costs.
Zhengyang Zhou   +4 more
doaj   +1 more source

Mesocarbon microbead densified matrix graphite A3-3 for fuel elements in molten salt reactors

open access: yesNuclear Engineering and Technology, 2021
This study aims to provide microstructural characterization for the matrix graphite which molten salt reactors (MSRs) use, and improve resistance to molten salt infiltration of the matrix graphite for fuel elements. Mesocarbon microbeads (MCMB) densified
Haoran Wang   +11 more
doaj   +1 more source

Processing‐Centric Innovative Strategies for Protonic Ceramic Electrochemical Cells

open access: yesAdvanced Energy Materials, EarlyView.
This review reveals how processing‐centric fabrication strategies govern architecture, microstructure, and interfaces in protonic ceramic electrochemical cells (PCECs), establishing a framework that translates materials innovation into scalable PCEC technologies.
Dongyeon Kim   +5 more
wiley   +1 more source

The Use of Additive Manufacturing Technologies for Molten Salt Reactors [PDF]

open access: yes, 2022
Teoretická část této bakalářské práce se zaměřuje na popis aktuálního výzkumu v oblasti solných reaktorů. Druhá polovina teoretické části pak shrnuje kovové aditivní metody. V praktické části se korozně porovnávají materiály konvenčně získané AISI 316L a
Matěj Tyc
core  

Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt

open access: yesScience and Technology of Nuclear Installations, 2021
Considering the necessity of the development of methods to reduce the burden of storage and disposal of high-level radioactive waste, in this study, we propose a nuclide separation technique using molten salt immersion.
Sang-Kwon Lee   +4 more
doaj   +1 more source

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