17 results about "Boiling water reactor" patented technology

Method for renovating a nuclear power plant initially comprising at least one light water nuclear reactor (LWR), in particular a pressurized water reactor (PWR) or boiling water reactor (BWR), replaced by at least one integrated modular nuclear reactor (SMR). The invention essentially consists of a method for retrofitting a nuclear power plant which consists of removing and removing all the components of the primary circuit with the exception of the LWR reactor vessel, which is emptied of all material and neutralized, then replacing in place of a part of these components with sub-assemblies each consisting of an integrated SMR reactor and a mixed concrete / metal structure which acts both as a reactor vessel for the SMR reactor, advantageously filled with water, as an anchor for the SMR inside the reactor building and advantageously as a contribution to the third containment barrier, while minimally modifying the infrastructure of the reactor building. Figure for abstract: Fig. 14D

The present invention relates to boiling water reactors arranged to receive a synthesis gas for producing raw gas products, such as a raw methanol product, particularly for transient operation, such as where the synthesis gas is at least partly provided by producing hydrogen by electrolysis of water or steam. Embodiments of the invention include a boiling water reactor, a method of revamping an existing boiling water reactor, and a process for producing raw gas product, such as raw methanol product, utilizing the boiling water reactor.

A nuclear fuel rod for a pressurised or boiling water reactor, the rod having a corrosion-resistant tube with an external surface comprising a textured pattern 100. The textured patter has first areas

During normal operation of a boiling water reactor, the thermal margin of the fuel assembly can be improved, and during shutdown and in the event of a reactivity-injected accident at cold temperatures, the void condensation effect can be reduced, thereby suppressing the rise in fuel enthalpy and reducing the risk of fuel rod damage. [Solution] A fuel spacer 15M is a component of a fuel assembly loaded into the core of a boiling water reactor, in which a plurality of fuel rods 11, each supported at both ends by an upper tie plate and a lower tie plate, are bundled together at intervals from one another. The spacer has a swirling vane 18 that generates a swirling flow in the coolant W flowing from the lower tie plate to the upper tie plate. The swirling vane is configured to be able to change direction so that it is tilted toward the fuel rods 11 during normal operation of the boiling water reactor, and faces in a vertical direction A along the lower tie plate to the upper tie plate when the boiling water reactor is shut down or when it is cold.

The present invention belongs to the technical field of nuclear fuel assembly test equipment, and specifically relates to a bulging and bursting test device for the inner cladding of a pressurized annular fuel rod. The bulging and bursting test device for the inner cladding of a pressurized annular fuel rod comprises a transition joint, an annular electric heating core assembly, an annular simulated core block, an inner cladding assembly, and an air intake pipe assembly. Through the arrangement of the above-mentioned structure and the connection of the various components therein, a large temperature difference can be formed in the circumferential direction of the inner cladding of the annular fuel rod to better simulate the temperature environment required for the test and completely simulate the heat transfer condition of the material from the outside to the inside. The bulging and bursting test device for the inner cladding of a pressurized annular fuel rod provided by the present invention can be applied to pressurized water reactors, boiling water reactors, heavy water reactors, fast reactors, power reactors, and marine power reactors.

A BWR channel box comprises a substrate, a first layer, and a second layer. The substrate comprises silicon carbide fibers. The first layer is deposited on a first surface of the substrate. The second layer is deposited on an opposite second surface of the substrate. Each layer comprises a corrosion resistant metallic composition. The combined weight of both layers is in a range from greater than 0% to 10% of the total weight of the channel box.

The present invention essentially comprises the steps of disassembling and removing all components of the primary circuit except for the LWR reactor vessel, which is essentially emptied and neutralized, and subsequently replacing some of these components with sub-assemblies each composed of an integrated SMR reactor and a concrete / metal hybrid structure, where this concrete / metal hybrid structure is also used as a reactor pit for the SMR reactor, which is preferably filled with water, and fixing the SMR inside the reactor building and contributing to a third containment barrier, preferably while minimizing damage to the infrastructure of the reactor building. The present invention is related to a method for retrofitting a nuclear power plant.

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.

To provide a reactor in which fluid easily flows.SOLUTION: A reactor 142 comprises a reactor pressure vessel 101, a reactor core 103 provided inside the reactor pressure vessel 101 and with fuel assemblies loaded therein, and a steam separator 105 provided inside the reactor pressure vessel 101 and separating water and steam from fluid 5 consisting of steam and water generated in the reactor core 103. The steam separator 105 comprises an annular channel that pours the fluid 5 from an upper part toward a lower part in its inside and opens at a lower part of the steam separator 105, and openings that drain bubbles in the fluid 5 flowing in the annular channel to the side part of the steam separator 105.SELECTED DRAWING: Figure 1

The invention relates to a method for preparing methanol. The method comprises the following steps: (a) preparing a hydrogen raw material through electrolysis; (b) providing a carbon oxide feedstock during the electrolysis operation in step (a); (c) mixing at least part of the hydrogen feed and a carbon oxide source consisting of a carbon monoxide and / or carbon dioxide feed to obtain methanol syngas; (d) adjusting the molar content of hydrogen, carbon monoxide and / or carbon dioxide in step (c) to a modulus M of 1.9 to 2.2, said modulus M being (H2-CO2) / (CO2 + CO); (e) converting the methanol syngas to methanol in one or more boiling water reactors; during the electrolysis inoperation in step (a): (f) interrupting the conversion of methanol syngas by heat exchange with boiling water in one or more boiling water reactors, in which step (f) the one or more boiling water reactors are heated by one or more auxiliary heaters to maintain boiling of water in the one or more boiling water reactors.

A methanol loop, and a methanol plant including said methanol loop, are provided. In addition to conventional components, the methanol loop comprises one or more additional heat exchangers, arranged to make best use of the heat energy in the effluent stream from the boiling water reactor. Processes for synthesising methanol in the methanol plants of the invention are also provided.

The disclosed concept relates to a novel modified and simplified Rankine steam-turbine cycle without rejection of heat in the cycle, which is driven by a thermocompressor (ejector) operating in the wet-vapor region, to the end of achieving of the maximum possible (˜100%) thermal efficiency of the thus modified Rankine cycle. Wet-vapor mixture circulating within the thermocompressor is being separated in a cylindrical separation tank, so that the saturated water is pumped to a water heater where it receives the cycle heat input, while the saturated vapor is expanded in a backpressure steam turbine producing useful mechanical work and is then recirculated back to the thermocompressor, where it is being re-pressurized by the primary fluid (pumped and heated saturated water). The concept can be applied to steam-turbine-cycle power-plants fueled by: coal or solid / liquid / waste fuel, nuclear fuel (using boiling water reactors, pressurized water reactors, pressurized heavy-water reactors, gas-cooled reactors, molten salt reactors or liquid-metal-cooled fast reactors) or renewable energy sources (Solar energy, biomass, geothermal), The concept can also be used in the form of the bottoming steam-turbine-cycle part of a combined gas-turbine / steam-turbine cycle power plant.

A methanol loop, and a methanol plant including said methanol loop, are provided. In addition to conventional components, the methanol loop comprises one or more additional heat exchangers, arranged to make best use of the heat energy in the effluent stream from the boiling water reactor. Processes for synthesising methanol in the methanol plants of the invention are also provided.

This invention relates to the monitoring and diagnosing of the nuclear power plant for both its thermal performance and safety using the NCV Method. Its applicability comprises any nuclear reactor such as used for research producing a useful output. Its greatest applicability lies with conventional Pressurized Water Reactor and Boiling Water Reactor nuclear plants generating an electric power. Its teachings of treating fission as an inertial process, a phenomena which is self-contained following incident neutron capture, allows the determination of an absolute neutron flux. This process is best treated by Second Law principles producing a total fission exergy. This invention also applies to the design of fusion thermal systems regards the determination of its Second Law viability and absolute plasma flux.

This invention relates to light water nuclear reactors, particularly pressurized water reactors (PWRs) or boiling water reactors, including an integrated autonomous passive decay heat removal system. The invention discloses a light water nuclear reactor (LWR), particularly a PWR or BWR, comprising: - a reactor core; - a system for removing at least some decay heat from the reactor core, comprising: a first water reservoir or pool disposed above the reactor core; a heat exchange device immersed in the pool; an organic Rankine cycle; a fluid loop; a second water reservoir different from the pool; and a second pump. The invention lies in installing an organic Rankine cycle and a supplementary water reservoir different from the pool, wherein the energy stored in the pool is the heat source for the organic Rankine cycle evaporator, and the supplementary water reservoir directly supplies the organic Rankine cycle condenser via a dedicated pump to constitute the cold source for the organic Rankine cycle condenser.

To provide a fuel assembly for boiling-water reactors capable of constraining a spacer to a specified height, and a reactor core.SOLUTION: A fuel assembly for boiling-water reactors is a fuel assembly for boiling-water reactors that includes multiple fuel rods, a spacer, and a channel box. The fuel assembly has: at least one recess on the inner wall of one side of the channel box for each constraint height of the spacer; a convex part at a position facing the recess when the spacer is set at a predetermined heigh on the outer surface of the spacer band facing the channel box; and an elastic material that is placed on the spacer band, facing the outer peripheral surface of the spacer band having the convex portion.SELECTED DRAWING: Figure 4