16 results about "Light-water reactor" patented technology

In order to ensure the structural integrity of a hood against a load such as pressure exerted from the outside of the hood, the present invention provides a steam dryer for a boiling water-type light-water reactor which ensures the stiffness of the hood without making the hood plate itself thicker, and which avoids lengthening the fabrication time or complicating the fabrication procedure. This steam dryer for a boiling water-type reactor comprises: a hood for guiding, to a steam dryer unit, steam separated by a gas-water separator installed above a reactor core made of a plurality of fuel assemblies disposed inside a nuclear reactor pressure vessel; a support ring; a skirt; and the steam dryer unit having a corrugated plate therein, the steam dryer being characterized in that the hood is made of a first hood plate disposed in the vertical direction, a reinforcing plate mounted on the first hood plate, a second hood plate disposed vertically above the first hood plate and the reinforcing plate, and a side plate disposed between the first hood plate and the steam dryer unit, and the reinforcing plate is formed such that the cross-section thereof is a concavo-convex shape.

The present invention relates to a dry storage module and a system comprising the same, the dry storage module having an improved mounting manner of a gas outlet and a cylinder body in a dry storage module for spent nuclear fuel of a vertical light water reactor, the dry storage module comprising: a housing forming a hexahedron-shaped accommodation space; a plurality of storage parts which are arranged in two rows in the accommodation space, are used for storing spent nuclear fuel, and extend for a long distance respectively; a hexahedron-shaped module part for accommodating the storage part; the storage tank is filled with spent nuclear fuel; a cartridge body surrounding the tank; a cartridge holder for attaching / detaching the cartridge body to / from the module part; the air inlet is formed in the side of the upper part of the shell; the air outlet is formed in the lower part of the shell; and shield grids provided at the respective inflow port and outflow port.

The invention relates to a nuclear cogeneration plant with a light water reactor (LWR) and a system for capturing atmospheric CO2 or for desalinating sea water without withdrawing liquid water therefrom or releasing same into the environment. The invention essentially consists in using, in combination, a thermal storage loop, arranged between the primary circuit and the secondary circuit of a reactor, with a system for capturing atmospheric carbon dioxide or for desalinating sea water at the condenser of the secondary circuit.

The invention belongs to the field of nuclear materials, and particularly relates to a nuclear fuel and a preparation method thereof and a reactor, the nuclear fuel comprises a nitride matrix and an MAX phase material distributed in the nitride matrix; the chemical formula of the MAX phase material is Mn + 1AXn, M is selected from at least one of Ti and Cr, A is selected from at least one of Si and Al, X is selected from C, and n is 1 or 2. According to the nuclear fuel disclosed by the invention, the MAX phase material is introduced into the nitride matrix, and a corrosion-resistant oxide layer is generated in situ by utilizing the MAX phase material to block water permeation, so that the nuclear fuel has the properties of high thermal conductivity, relatively strong water corrosion resistance, steam oxidation resistance and radiation resistance, and can be applied to a light water reactor; the application risk of the existing uranium nitride fuel in the light-water reactor is reduced, and the safety and economy of the reactor are improved.

As one way of preparing for global cooling, we will provide a nuclear reactor that requires less investment capital, is based on the premise that population density will decrease due to population decline, and it is unknown when, where, and what scale an earthquake will occur, and of course does not require a final disposal site, and can convince the media and local residents by reducing the amount of spent nuclear fuel from light water reactors. [Solution] A nuclear reactor in which a large number of allowable alloy-containing nuclear fuel rod assemblies 1, each consisting of a large number of allowable alloy-containing nuclear fuel rods made of heavy noble gas coolant and allowable enrichment plutonium alloy, are arranged in a square lattice pattern in the core of an existing BWR.

The present invention relates to a nuclear cogeneration plant comprising a light water reactor (LWR) without extracting or releasing liquid water into the environment and a system for capturing atmospheric CO2 or desalination of seawater. The invention essentially consists in the combined use of a heat storage loop arranged between the primary and secondary circuits of the nuclear reactor, together with a system for capturing atmospheric CO2 or desalination of seawater in the condenser of the secondary circuit.

To provide a nuclear reactor that is decreasing light water reactor spent nuclear fuel to persuade the media of mass communication and local residents, not to mention no need for a final disposal site, on the premise that inhabitants are decreasing and the population density is small and that it is unknown when and where what scale of earthquake takes place.SOLUTION: The breeding performance is enhanced with heavy gas cooling material and nuclear fuel low in plutonium enrichment, and the nuclear fuel is burnt to enhance the plutonium enrichment of the nuclear fuel. Simple processing of only removing fission products from the used nuclear fuel is only required. Although even photovoltaic power generation facilities exploded, dumped objects will increase in future when the power selling price decreases to 8 yen / kwh under a trade guidance (Chinese products may be used as fences in EU and as sunshades in Japan.). The nuclear reactor may take advantages thereof.SELECTED DRAWING: Figure 1

A method for retrofitting a nuclear power plant which include dismantling and removing all the components of the primary circuit apart from the LWR reactor vessel, which is essentially emptied of all material and neutralized, subsequently replacing a part of these components with subassemblies that are each made up of an integrated SMR reactor and a mixed concrete / metal structure, which mixed concrete / metal structure is also used as a reactor pit for the SMR reactor, which reactor pit is advantageously filled with water, anchoring the SMR to the inside of the reactor building and advantageously contributing to the third confinement barrier while ensuring minimal disruption to the infrastructure of the reactor building.

The dual isolation valve system for a fuel transfer tube in a pressurized light water reactor nuclear power plant, according to the present invention, is characterized in that: in order to withdraw nuclear fuel from a fuel building and reload nuclear fuel into a reactor within a reactor building through a fuel transfer tube, a motor-operated gate isolation valve and a manual isolation valve are installed at the front side of the fuel transfer tube, relative to the fuel building side, in order to fill and drain a reactor refueling water storage tank; the manual isolation valve on the fuel building side is maintained in an open state; a plurality of disc-fastening holes are formed along the outer circumference of the disc of the motor-operated gate isolation valve; a disc protrusion is inserted into the inside of the fuel transfer tube; a disc step circumference is larger than the outer diameter of the fuel transfer tube so as to seal the fuel transfer tube; and the disc of the motor-operated gate isolation valve moves downward due to the driving of a motor (M), causing the motor-operated gate isolation valve to block the fuel transfer tube and maintain the tube in a closed state, the disc being an isolation valve disc that functions as a blind flange.

A nuclear power plant with a light water reactor (LWR) and a thermal storage cycle connected to a heat network and arranged in thermal parallel with the reactor's conversion cycle. The invention essentially consists of using a thermal storage loop (13) in thermal parallel with the secondary circuit (5) of a nuclear reactor. Figure for the abstract: Fig. 3

The invention discloses a method for connecting silicon carbide ceramics through spark plasma sintering assisted by a titanium foil interlayer, and belongs to the technical field of ceramic connection. In order to optimize the performance of a silicon carbide ceramic material in a nuclear environment, by adopting a spark plasma sintering (SPS, also known as a current field assisted sintering technology) ceramic connection technology, metal titanium is selected as a silicon carbide connection middle layer, and meanwhile, proper connection temperature, heat preservation time and connection layer thickness are selected, so that the silicon carbide ceramic material which is high in connection strength and good in heat preservation performance is obtained. According to the connection structure, the reliability of the silicon carbide ceramic material serving as a fuel cladding material of a light water reactor (LWR) in the nuclear power field is improved.

The present invention relates to a nuclear power cogeneration plant having a light water reactor (LWR) and a system for capturing atmospheric CO2 or desalinating seawater without extracting liquid water therefrom or releasing liquid water into the environment. The invention mainly consists in using a heat storage loop arranged between the primary circuit and the secondary circuit of the reactor in combination with a system for capturing atmospheric carbon dioxide or desalinating seawater at the condenser of the secondary circuit.

To provide a fast reactor core capable of improving core performance by devising a loading method for TRUs with different impurity FP content, recovered through advanced reprocessing of spent fuel from light water reactors and fast reactors, and improving nuclear properties.SOLUTION: A fast reactor core 1 is a reactor core that is loaded with a radial fast reactor-origin metallic fuel 34, which includes Pu recovered from reprocessed fast reactor spent fuel, and a radial light water reactor-origin metallic fuel 33, which includes Pu recovered from reprocessed light water reactor spent fuel. The radial light water reactor-origin metallic fuel 33 is loaded adjacent to the radial blanket fuel assembly 5 around the fast reactor core 1, and the radial fast reactor-origin metallic fuel 34 is loaded at a position closer to the center of the fast reactor core 1 than the radial light water reactor-origin metallic fuel 33.SELECTED DRAWING: Figure 2

The invention discloses a nuclear wear-resistant high-entropy alloy coating as well as a preparation method and application thereof, and belongs to the technical field of high-entropy alloy coatings, Fe35-45Ni35-45Cr5-15Al3-7Ti3-7 high-entropy alloy coatings are prepared by a plasma spraying method, the existing Co-based or Co-containing high-entropy alloy coating is easy to transmutation, the transmutation rate is high, and the transmutation rate is high. A stable FCC solid solution structure is formed through a high-entropy effect; the corrosion resistance is improved by the element Cr, a compact Al2O3 / TiO2 oxidation film can be formed by the elements Al and Ti at high temperature, the oxidation resistance and the corrosion resistance are remarkably enhanced, and the corrosion-resistant aluminum alloy is particularly suitable for the protection requirements of a light water reactor and a fourth-generation nuclear reactor.

The present invention relates to a light water reactor nuclear fuel rod loading device, which can measure the loading force of nuclear fuel rods acting on each unit of a support grid in an environment identical to the nuclear fuel rod loading environment, so as to provide a data basis for optimizing the nuclear fuel assembly process. According to the light water reactor nuclear fuel rod loading device of the present invention, the light water reactor nuclear fuel rod loading device includes a grid support and a loading power device. The loading power device is provided with a traction module that reciprocates towards the grid support. The light water reactor nuclear fuel rod loading device further includes: a hollow cladding tube sample, located on one side of the support grid fixed by the grid support, having the same diameter as the nuclear fuel rod cladding tube; a tie rod, one end of which passes through the unit of the support grid during use and is configured to be coupled to the cladding tube sample, and the other end of which is configured to be coupled to the traction module; and a measuring mechanism, provided on the tie rod, for measuring the loading force of the traction module pulling the tie rod.

Provided is a light water reactor uranium fuel assembly capable of reducing the heat generation amount of both Am-241 and Cm-244, which are causes of glassification, by a light water reactor alone without using a fast neutron reactor, and capable of reducing the amount of glassification. A light water reactor uranium fuel assembly for a nuclear fuel cycle in which an americium isotope is extracted at the time of reprocessing of used fuel and the extracted americium isotope is added to the nuclear fuel cycle, the weight ratio W (wt% unit) of the added americium 241 with respect to the weight of the fuel heavy metal being W < -0.006e with respect to the average uranium 235 enrichment e (wt% unit) of the fuel assembly 2 +0.12e-0.43 (enrichment 5 wt% or more), W < -0.000356e+0.00357 (enrichment 4.2 wt% or more and less than 5.0 wt%).