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Latest Publications & Patents on Small Modular Reactors (SMRs)

Small Modular Reactors

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Small modular reactors
Small modular reactors revolutionize nuclear power through standardized, factory-built designs for faster and cost-effective deployment.

Small modular reactors are nuclear fission power systems with electrical output capacity typically below 300 MWe per unit, designed from the outset for factory fabrication of standardized modules, road or rail transport to site, and accelerated construction schedules — a deliberate structural inversion of the gigawatt-scale custom-built nuclear plants whose capital cost overruns and decade-long construction timelines effectively halted new nuclear deployment across Western markets after the 1980s.

Reactor physics and coolant chemistry vary substantially across the design portfolio — advanced light water reactors extending proven pressurized water technology at reduced scale, molten salt reactors dissolving fuel directly in fluoride or chloride coolant, high-temperature gas-cooled reactors using helium and TRISO fuel particles, sodium-cooled and lead-cooled fast spectrum designs, and thermal microreactors targeting remote industrial or military sites below 10 MWe.

The publications and patents indexed below address reactor physics, thermal hydraulics, passive safety validation, fuel assembly design, materials qualification under irradiation, factory manufacturing processes, licensing methodology, and techno-economic assessments across this full design spectrum.

This is our latest selection of worldwide publications and patents in english on Small Modular Reactors (SMRs), between many scientific online journals, classified and focused on small modular reactor, SMR, nuclear microreactor, advanced light water reactor, molten salt, high-temperature gas-cooled reactor, lead-cooled fast reactor, sodium-cooled fast reactor, SMR passive safety system, SMR cogeneration, SMR district heating, HALEU fuel SMR, SMR containment design and SMR decommissioning.

Heated base for salt tank

Patent published on the 2026-10-15 in US under Ref US20260323779 by TERRAPOWER LLC [US] (Stuart Joshua [us])

Abstract: A heated foundation system for supporting a molten salt thermal storage tank comprises a concrete ring wall, cellular glass insulation blocks disposed within the concrete ring wall, a layer of fire bricks arranged on top of the cellular glass insulation blocks, and a plurality of doped fire bricks positioned within the layer of fire bricks proximate an outer perimeter of the foundation. The doped fire bricks include a conductive coating or dopant, which enables them to generate heat via electric[...]


Our summary: The system features a concrete ring wall and cellular glass insulation. Doped fire bricks generate heat through electrical resistance. A control system manages heating zones for uniform temperature distribution.

thermal storage, heated foundation, doped fire bricks, temperature control

Patent

Molten salt synthesis of uranium nitride

Patent published on the 2026-10-15 in US under Ref US20260317172 by OREGON STATE UNIV [US] (Augustine Victoria Lee [us], Chemey Alexander Theodore [us], Mcglamery Devin Gray [us])

Abstract: A method for producing uranium nitride, the method including: heating a vessel containing a blend including a uranium source, a chloride salt, a metal nitride, and a reductant under a non-participating cover gas, wherein the vessel is maintained at a reaction temperature and for a reaction time sufficient to produce a molten reaction mixture including the uranium nitride; and isolating the uranium nitride, wherein the uranium source is a uranium oxide or a uranium halide. A system for producing [...]


Our summary: The method involves heating a blend of uranium source, chloride salt, metal nitride, and reductant in a vessel. A non-participating cover gas is used while maintaining a specific reaction temperature. The process results in a molten mixture from which uranium nitride is isolated.

Uranium nitride, Molten salt synthesis, Non-participating cover gas, Reaction temperature

Patent

Molten salt synthesis of uranium carbide

Patent published on the 2026-10-15 in US under Ref US20260317178 by OREGON STATE UNIV [US] (Mcglamery Devin Gray [us], Chemey Alexander Theodore [us], Augustine Victoria Lee [us])

Abstract: [0000] A method for producing uranium carbide, the method including: heating a vessel containing a blend including a uranium source, a chloride salt, a carbon source, and a reductant under a non-participating cover gas, wherein the vessel is maintained at a reaction temperature and for a reaction time sufficient to produce a molten reaction mixture including the uranium carbide; and isolating the uranium carbide, wherein the uranium source is a uranium oxide or a uranium halide. A system for pro[...]


Our summary: The method involves heating a blend of uranium source, chloride salt, carbon source, and reductant in a vessel. The process produces a molten reaction mixture containing uranium carbide. The system includes a heating element and a processing zone for isolating the uranium carbide.

uranium carbide, molten salt synthesis, reaction temperature, non-participating cover gas

Patent

Method for producing metal carbide, carbide composition, and electrolysis device

Patent published on the 2026-10-08 in WO under Ref WO2026211117 by THE DOSHISHA [JP] (Isogai Tomohiro [jp], Tsuchii Takane [jp], Yamauchi Akiyoshi [jp], Kishikawa Yosuke [jp], Goto Takuya [jp], Suzuki Yuta [jp], Tanaka Seiya [jp], Watanabe Takashi [jp])

Abstract: According to the present invention, substantial current efficiency can be further improved when a metal carbide is produced by means of a method for producing a metal carbide which includes: preparing a molten salt that contains first metal ions and carbonate ions; arranging a working electrode and a counter electrode in an electrolytic cell and supplying a current between the working electrode and the counter electrode so as to obtain a carbide composition that contains a carbide of the first m[...]


Our summary: The method involves preparing a molten salt with metal and carbonate ions. An electrolytic cell is used to supply current between electrodes to produce metal carbide. The carbide composition is then recovered in a designated recovery unit.

metal carbide, electrolysis, molten salt, current efficiency

Patent

Conversion of used nuclear fuel to a soluble molten salt form using strongly reducing metal and contolled reoxidation for uranium and transuranic sepa

Patent published on the 2026-09-23 in GB under Ref GB2704839 by MOLTEX ENERGY CANADA INC [CA] (Jose Pablo Zuniga Villegas [ca])

Abstract: A method for processing spent nuclear fuel comprising uranium and one or more transuranic elements, and/or compounds thereof, the process comprising: converting the spent nuclear fuel into a fine powder, the powder containing uranium oxide, and oxides of the transuranic elements, by heating in oxygen (by a voloxidation or OREOX process); optionally reducing the powder by heating in a gas containing hydrogen followed by reoxidation with a gas containing oxygen with the cycle repeating one or more[...]


Our summary: This method processes spent nuclear fuel into a fine powder containing uranium and transuranic oxides. It involves converting the powder into a molten salt mixture with a reducing metal to solubilize uranium species. The process includes reoxidation to precipitate uranium oxides and separate insoluble materials.

Nuclear fuel processing, Molten salt, Reducing metal, Uranium separation

Patent

Controlled titration with strongly reducing metals for selective molten salt extraction and recovery of tranuranics elements from used nuclear fuel

Patent published on the 2026-09-23 in GB under Ref GB2704933 by MOLTEX ENERGY CANADA INC [CA] (Ian Richard Scott [gb], Jose Pablo Zuniga Villegas [ca])

Abstract: A titration-based process for selectively extracting transuranic elements from used nuclear fuel in a molten salt system. The process involves converting spent fuel into a fine powder, mixing it with a molten halide salt, and adding a precisely controlled amount of a strongly reducing metal. Real-time redox monitoring ensures optimal extraction of transuranics while limiting uranium dissolution, and can use the colour or electrochemical potential of the molten halide salt. This method improves s[...]


Our summary: This process enables selective extraction of transuranic elements from used nuclear fuel using a controlled titration method with reducing metals. It involves converting spent fuel to powder, mixing with molten halide salt, and real-time redox monitoring to optimize extraction. The method enhances separation efficiency, minimizes waste, and allows for the reuse of extracted materials in advanced reactors.

Titration, Transuranics, Molten Salt, Redox Monitoring

Patent

Study on Flow Field Excitation and Rotor Shaft Response of the High-Temperature Molten Salt Circulating Primary Pump

Published on 2026-01-31 by Xiongfa Gao, Xinyi Zhang, Weidong Shi, Daohong Wang, Ruijie Zhao, Zhiyu Zhu @MDPI

Abstract: This study examines the impact of fluid excitation forces on the dynamic response of high-temperature molten salt circulating primary pump rotor systems. Unsteady simulations were conducted in ANSYS CFX to characterize pressure pulsation and radial forces across all impeller stages. Critical speeds and vibration modes were subsequently analyzed using SAMCEF to evaluate transient responses under varying flow rates. Key findings: Numerical performance predictions align with experimental data withi[...]


Our summary: This study analyzes the impact of fluid excitation on the dynamic response of high-temperature molten salt pump rotors. Unsteady simulations in ANSYS CFX characterize pressure pulsations and radial forces, while critical speeds and vibration modes are evaluated using SAMCEF. Key findings indicate that numerical predictions align closely with experimental data, revealing significant variations in radial forces across impeller stages.

Fluid Excitation, Rotor Dynamics, Pressure Pulsation, ANSYS CFX

Publication

Multicriteria Assessment for Technological Readiness

Published on 2026-01-29 by Jorge Omar Gil Posada, Juan Carlos Quintero-Daz, Andrs A. Amell @MDPI

Abstract: In addressing the increasing global energy demand, this manuscript compares four distinct processes for hydrogen production from natural gas (NG): steam methane reforming (SMR), dry methane reforming (DMR), autothermal reforming (ATR), and catalytic methane decomposition (CMD). The comparison emphasizes their respective efficiencies and environmental impacts. Simulations were conducted using the Peng&amp;ndash;Robinson model, implemented in the DWSIM 8.8.3 software package, considering comme[...]


Our summary: This manuscript compares four hydrogen production processes from natural gas: SMR, DMR, ATR, and CMD. It evaluates their efficiencies and environmental impacts using the TOPSIS method, identifying ATR as the best option. The study highlights Colombia s potential in the hydrogen economy based on its natural resources.

Hydrogen production, Multicriteria assessment, Environmental impact, TOPSIS method

Publication

Topics covered: Small Modular Reactors, nuclear fission, factory fabrication, electrical output capacity, accelerated construction, reactor physics, coolant chemistry, advanced light water reactors, molten salt reactors, high-temperature gas-cooled reactors, thermal microreactors, passive safety validation, fuel assembly design, materials qualification, licensing methodology, techno-economic assessments, standardized modules, International Atomic Energy Agency, ISO 9001, ASME NQA-1, IEEE 7-432, and IEC 61513..

Glossary of Terms Used

International Organization for Standardization (ISO): a non-governmental international body that develops and publishes standards to ensure quality, safety, efficiency, and interoperability across various industries and sectors, facilitating global trade and cooperation. Established in 1947, it comprises national standardization organizations from member countries.

Radiology Information System (RIS): a software system for managing medical imaging data, facilitating scheduling, tracking, and reporting of radiological procedures, and integrating with other healthcare systems to enhance workflow and patient care.

Small Modular Reactors (SMR): compact nuclear reactors designed for modular construction, enabling scalable deployment and enhanced safety features. Typically generating up to 300 megawatts of electricity, they can be factory-built and transported to sites, reducing construction time and costs compared to traditional large reactors.

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10th year anniversary

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