13 results about "Molten salt reactor" patented technology

This invention relates to the field of high-temperature resistant metal structural materials for molten salt reactors, specifically to a Ni-W-Mo-Cr series high-temperature resistant multi-principal element alloy for molten salt reactors and its preparation method. The Ni-W-Mo-Cr series high-temperature resistant multi-principal element alloy for molten salt reactors is composed of four elements: Ni, W, Mo, and Cr. The atomic percentages of each element in the alloy are as follows: Ni 55~70 at.%, W 5~10 at.%, Mo 10~17 at.%, Cr 12~20 at.%, with a total content of 100 at.%. Through precise design of the multi-principal element alloy composition, this Ni-W-Mo-Cr series high-temperature resistant multi-principal element alloy for molten salt reactors achieves a stable FCC tough matrix and a BCC dispersed strengthening phase, forming a two-phase solid solution structure. Simultaneously, it avoids the precipitation of TCP-type brittle intermetallic compounds in the alloy, achieving a synergistic match between strength and plasticity under high-temperature conditions of 850℃, meeting the stringent long-term service requirements of molten salt reactors.

The utility model relates to the field of nuclear energy and is intended for the purification of circulating fluoride salt melts in molten salt reactor installations, including those implementing the thorium fuel cycle. The method includes taking a portion of the circulating melt from the main circulation circuit of the reactor, directing said portion of the melt through a bypass line into a sorption-filtration module, passing the melt through a filter layer and returning the purified melt back to the circulation circuit. Filtration is carried out through a sorption-filtration material based on modified diatomite with a porosity of 60–85% and a pore size of 5–200 µm, formed as granules, porous blocks, or multilayer filtration cassettes. The technical result consists of increasing the purification efficiency of the circulating fluoride salt melt due to the simultaneous mechanical retention of solid particles and the sorption binding of colloidal impurities. The utility model was developed within the framework of the implementation of the scientific and technical program IRN BR24993225 for program-targeted financing of the Science Committee of the Ministry of Science and Higher Education of the Republic of Kazakhstan for 2024–2026.

This invention relates to the field of solid waste treatment technology, and particularly to a device and method for determining the fusibility of solid waste incineration fly ash. The device includes: a heating furnace, a corundum tube, a molten salt reactor, and a recording unit. The corundum tube is disposed inside the heating furnace, with its opening located outside the furnace. The molten salt reactor is disposed inside the corundum tube and contains molten salt and solid waste incineration fly ash, which is impregnated in the molten salt. A thermocouple is installed inside the heating furnace to measure the temperature inside the corundum tube. The recording unit records the real-time area of ​​the solid waste incineration fly ash during the heating process through the opening of the corundum tube. This method can effectively determine the fusibility of solid waste incineration fly ash.

This application provides a thorium-based molten salt reactor system with isolated fuel salt and breeder salt, and its operation method. The system includes: a primary loop system, comprising a reactor body, a fuel salt loop, fuel salt circulating in the fuel salt loop, a breeder salt loop, and breeder salt circulating in the breeder salt loop, wherein the fuel salt contains uranium-233 but does not contain thorium-232, and the breeder salt contains thorium-232 but does not contain fissile nuclear fuel; the fuel salt loop and the breeder salt loop are physically isolated within the reactor body and neutronically coupled; the reactor body includes a main vessel and multiple fuel assemblies disposed therein, each fuel assembly including a fuel tube made of insulating material, the two ends of which are respectively sealed to a lower chamber and an upper chamber within the main vessel; the fuel tube is externally wrapped with moderator blocks, and flow channels are formed between the moderator blocks; the fuel salt of the fuel salt loop flows through the interior of the fuel tube, and the breeder salt of the breeder salt loop flows through the flow channels between the moderator blocks.

This invention discloses a nuclear power generation and hydrogen production integrated utilization system, relating to the field of nuclear power hydrogen production technology. The key technical point is that by simultaneously distributing the high-temperature thermal energy of a molten salt reactor to a supercritical carbon dioxide Brayton cycle power generation system and a three-step vanadium-chlorine thermochemical cycle hydrogen production system, a new parallel-coupled, cascaded energy conversion architecture is constructed. This fundamentally overcomes the drawback of mismatch between heat grade and energy demand in traditional series-type nuclear power integrated utilization schemes. This design not only enables efficient power generation from high-temperature thermal energy and gentle hydrogen production from mid-temperature thermal energy, but also achieves deep recovery of waste heat through an internal heat exchange network, significantly improving the overall energy utilization efficiency of the system. The invention demonstrates significant technological progress in improving energy utilization efficiency, reducing production costs, and decreasing carbon emissions, providing a practical technical path for the multi-product integrated utilization of nuclear energy and large-scale green hydrogen production.

The present invention relates to an optimized geometric design for Small Modular Molten Salt Reactors (SM-MSR) operating in the fast neutron spectrum. The SM-MSR of the present invention, incorporates a symmetrical structure with six input and six output points. The triangular curves between these inlets and outlets direct the flow of liquid fuel, optimizing the mixture and eliminating recirculation zones. The design ensures a homogeneous flow of liquid fuel salt within the reactor core, preventing the formation of recirculation zones. This feature improves the neutronic and thermo-hydraulic performance of the reactor, prevents thermal stresses that may occur in the blanket walls, and increases heat transfer efficiency.

This description relates to a method (300) for determining, by a computing device, a fuel salt composition of a molten salt nuclear reactor, the method comprising: - the determination of neutron fluxes (ϕ(E)) of several energies and a multiplication factor by a step of solving (302) a neutron transport equation; - the determination, for each of the nuclides, of condensed microscopic cross sections from the neutron fluxes (ϕ(E)); - the determination (303) of the weights of the nuclides on the multiplication factor from the condensed microscopic cross sections; and - the determination (304), from the weights of the nuclides, of a fuel salt inventory including at least one calculation of the evolution of the nuclides, by a step of solving (306) evolution equations, such that the evolution inventory complies with at least one operating condition.

The present invention relates to a fuel salt feeding apparatus (8) for a molten salt reactor (MSR), comprising: a fuel container (9) for holding fuel salt units; a feeding pipe (11) connected to the fuel container for transferring fuel salt units from the fuel container to a molten salt container (12); a valve structure (1) on the feeding pipe, said valve structure comprising: a bucket member (4, 14) having a fuel salt unit compartment (7) for containing one or more fuel salt units, and a bucket member position detector; a release valve (15) on the feeding pipe downstream from the valve structure, said release valve comprising a release valve position detector; a fuel salt unit detector (16) on the feeding pipe.

The present invention relates to a molten salt reactor system comprising a reactor vessel comprising a reactor core in an upper compartment, and one or more drain tanks situated in a lower compartment below the upper compartment, and a molten fuel salt pump, and a heat exchanger, wherein a molten fuel salt flow direction is provided in a fuel salt loop, said fuel salt loop comprising the reactor core, the one or more drain tanks, the molten fuel salt pump, and the heat exchanger, the direction of the molten fuel salt flow is from the heat exchanger towards the reactor core, wherein (a) the one or more drain tanks are located between the reactor core and the molten fuel salt pump in the molten fuel salt flow direction and the molten fuel salt pump is located between the one or more drain tanks and the heat exchanger in the molten fuel salt flow direction and the heat exchanger is located between the molten fuel salt pump and the reactor core in the molten fuel salt flow direction and the reactor core is located between the heat exchanger and the one or more drain tanks in the molten fuel salt flow direction, or (b) the molten fuel salt pump is located between the reactor core and the one or more drain tanks in the molten fuel salt flow direction and the one or more drain tanks are located between the molten fuel salt pump and the heat exchanger in the molten fuel salt flow direction and the heat exchanger is located between the one or more drain tanks and the reactor core in the molten fuel salt flow direction and the reactor core is located between the heat exchanger and the molten fuel salt pump in the molten fuel salt flow direction, wherein the lower compartment is provided with a passive decay heat removal system.

This invention discloses a flash metallurgical system based on photothermal power generation and photolysis hydrogen production. The photolysis hydrogen production system collects solar energy and produces hydrogen through photolysis of water. The flash smelting system uses the hydrogen produced by the photolysis hydrogen production system to smelt metals. The integrated compressed air energy storage and generation system generates electricity through a turbine air generator to power the flash smelting system. The automatic control system uses a PLC programmable logic controller to coordinate and control the photolysis hydrogen production system, the flash smelting system, and the integrated compressed air energy storage and generation system. This system mainly uses a high-temperature molten salt reactor as the direct heat source for flash metallurgy. The photolysis hydrogen production system produces the hydrogen required for the metal reduction reaction, eliminating the dependence of metal smelting systems on traditional fossil fuels and enabling more efficient and high-quality completion of the metal smelting process. The use of compressed air energy storage and a turbine air generator system replaces the traditional steam power generation system, reducing dependence on water resources.

Method for determining the fuel salt composition of a molten salt reactor. This description relates to a method (300) for determining, by a computing device, the fuel salt composition of a molten salt nuclear reactor, the method comprising: - the determination of neutron fluxes (ϕ(E)) of several energies and a multiplication factor by a step of solving (302) a neutron transport equation; - the determination, for each of the nuclides, of condensed microscopic cross sections from the neutron fluxes (ϕ(E)); - the determination (303) of the weight of the nuclides on the multiplication factor from the condensed microscopic cross sections;and- the determination (304), from the weights of the nuclides, of a fuel salt supply inventory including at least one calculation of the evolution of the nuclides, by a step of solving (306) evolution equations, so that the evolution inventory respects at least one operating condition. Figure for the abstract: Fig. 3;

The utility model provides a kind of for liquid fuel thorium-based molten salt reactor fluorine-containing gas processing adsorption device prototype, including vertical cylinder, the inside of vertical cylinder is sequentially provided with filter cavity, active alumina filling cavity and dust collection cavity from top to bottom, and the filter cavity, active alumina filling cavity and dust collection cavity are interconnected between, the bottom and top of vertical cylinder are provided with air inlet and air outlet respectively, the air inlet is connected with the dust collection cavity, the air outlet is connected with the filter cavity. For the utility model, by the filter cavity, the active alumina filling cavity and the dust collection cavity, fluorine gas in liquid fuel thorium-based molten salt reactor can be removed, the safety, reliability and convenience of gas path system of thorium-based molten salt reactor are improved.

The present application relates to the technical field of heavy oil processing, and particularly relates to a method and device for liquid oil pyrolysis and co-production of carbon materials, which comprises the following steps: feeding liquid heavy oil into an electrically heated molten salt reactor through a continuous feeding system, wherein the molten salt reactor is filled with molten alkaline salt medium; performing catalytic pyrolysis of the oil in the liquid phase environment of the molten salt medium, and the residence time of the oil in the molten salt is 5-10s; the liquid oil is uniformly cracked in the molten salt liquid phase to produce low-carbon hydrocarbon gas, hydrogen and dispersed fine carbon particles, and the carbon particles are suspended on the surface of the molten salt under the action of the molten salt buoyancy and do not deposit and aggregate; the suspended carbon particles are collected from the surface of the molten salt in real time through a mechanical push rod continuous collection system; the method can realize continuous and stable pyrolysis of heavy oil and efficient and continuous separation of products in the liquid phase molten salt environment, improve the production efficiency, and ensure the stability of the product quality.