321results about "Nuclear power plant details" patented technology

An offshore, floating, moored, nuclear power generating plant and multi-purpose platform is disclosed herein. In a preferred embodiment, the invention consists of a spar or cell spar platform with multi-purpose, all weather topside decks, attached to a submerged “dry tank” that further includes: reactor generator deck(s), power plant main control deck, and central plant deck, that are all integrated within a watertight ballast hull. The invention design further includes cells that are modular for facilitating factory assembly and ultimate construction in a shipyard environment. Reactor vessels are typical naval nuclear reactor having a time tested outstanding safety record. A plurality of reactor generator modules are interconnected and operate independently and collectively and are transmitted by a plurality of high voltage direct current (HVDC) submarine cables through a transformer to the electrical grid. Multipurpose topside decks house vessel commend, crew, and any ancillary and co-generation equipment. The present invention, constructed in a multi-path manufacturing process, provides exceptional economic, environmental, sustainability, security, safety, and operational advantages over the current art of power generation.

At least one pair of hodoscope radiation monitors arranged to simultaneously monitor a target region that contains a source of radiation. The hodoscopes are preferably arranged so that their fields of view of the region are approximately orthogonal. The fields of view of the two detectors will overlap in a region that contains the source of radiation. Each of the two detectors will record radiation from the overlap region and, in addition, will record background radiation emanating from other regions within detector fields of view. The present invention provides statistical correlation techniques to estimate the extent to which unusually high radiation originates in the overlap region, irrespective of background in the field-of-view of individual hodoscope detectors. The source of radiation might be spontaneous, might be from an activation process, or might be scattered in from an external beam.

A photocatalytic substance having the properties of an n-type semiconductor is deposited on a surface of a metal base made of a stainless steel or Inconel. When necessary, the hydrogen concentration of the reactor water is increased. A current produced by the photocatalytic substance when the same is irradiated with light or radioactive rays in a nuclear reactor flows through the metal base to reduce corrosion current. When necessary, the photocatalytic substance is provided on its surface with at least one of Pt, Rh, Ru and Pd.

The object of this invention is to provide a method for mitigating a stress corrosion cracking of reactor structural material which makes it possible to suppress the rise in the main steam line dose rate without secondary effects such as a rise in the concentration of radioactive cobalt-60, etc. in the reactor water. Hydrogen and a reductive nitrogen compound containing nitrogen having a negative oxidation number (for example, hydrazine) are injected into the core water of boiling water nuclear power plant. By injecting the reductive nitrogen compound containing nitrogen having a negative oxidation number into the core water, the stress corrosion cracking of structural material of reactor can be mitigated without side reactions such as a rise in the concentration of cobalt-60, etc.

The invention provides a microthruster which includes a housing having a propellant container and a discharge section, means to heat the propellant to drive vapors toward the discharge section, a heating element to heat the vapors and one or more ports to discharge the vapors to provide thrust. Further provided is a method for powering a microthruster by flowing gas in free molecular flow therein so that a plurality of molecules of the gas contact a heating element before discharge from the microthruster.

A device for slowing down and disintegrating a plug of liquid plunging forward in a duct includes a container having a bottom and an opposite inlet, which is connectable to the duct and through which the plug of liquid can be directed into a central, axial trajectory in the container. Inside the container is an inner tube, open towards the bottom, which separates an inner hollow space from an outer, cross-section-wise ring-shaped hollow space, a distributor body being arranged in the trajectory of the entering plug of liquid for splitting and disintegrating the plug of liquid as well as throwing out the disintegrated constituent parts of liquid in the direction outwards from the center. The bottom includes a concavely curved guide surface for diverting the liquid from one of the hollow spaces to the other to reverse the direction of motion of the liquid. A corresponding method is also provided.

A loose parts collection weir that is a nearly cylindrical structure that is integrally attached to the lower deck plate or sludge collector top plate of a steam generator to retain loose parts along the feedwater and recirculation water transit path to the tube bundle. The weir is a near vertical structure built into the upper drum of the steam generator, near the periphery of the lower deck plate or sludge collector top plate in the vicinity of the downcomer annulus. The weir may contain a radially inwardly projecting lip which forms a pocket for loose parts to collect. As the feedwater flows toward the downcomer annulus, loose parts will tend to deposit onto the lower deck plate aided by gravity and be trapped by the loose parts collection weir.

A system and method isolate a nuclear power plant from effects of seismic action. An artificial lake is formed as a depressed area in the ground surrounded by walls or banks to constrain a volume of water within the depressed area. The lake has a concrete reinforced bed. The lake is surrounded by a land-based support area. The lake is filled from a source of water in liquid communication with the lake. The source is controlled to release water into the lake to maintain the lake at a selected level. At least one vessel floats on the surface of the water. The vessel is connected to the walls or banks of the lake with a plurality of shock absorbers to dampen movement of the vessel. A nuclear power plant erected on the vessel includes at least one cooling tower that receives cooling water from the lake.

The present invention provides a module structure and a plant construction method capable of easily attaching a facility device of a plant and shortening a plant construction period. The module structure of the present invention includes a support member which temporarily supports a facility device component to be arranged in a cell constituting a plant at a designed position and which constitutes scaffolding for attaching the facility device component and forming the cell, a box-shaped frame which is possible to be carried into inner space of the cell while fixing the support member, and joint means which is detachably attachable and which temporarily assembles the support member and the frame.

Ceramic materials that are highly resistant to strong acids such as concentrated sulfuric acid and halides such as hydrogen iodide are employed to make block elements through which a large number of circular ingress channels extend in perpendicular directions and which are joined and piled in the heat exchanging medium section to provide a compact heat exchanger that excels not only in corrosion resistance but also in high-temperature strength.

The invention relates to a propulsion device comprising a gas ejection nozzle and an injection chamber for injecting at least one propellant fluid. According to the invention, the device has an induction loop which surrounds a zone of the nozzle and also an electricity generator to feed said induction loop, in particular under drive from a heat engine whose heat source is a nuclear core and whose heat sink is a cryogenic liquid which is subsequently used for propulsion.

The invention is applied to the field of nuclear power control and provides a steam generator water-level control method, device and nuclear power plant of a nuclear power generating unit. The method comprises the following steps of: detecting a parameter associated with steam generator water-level control; obtaining an operation inlet and an equipment operating state associated with the steam generator water-level control; outputting the detected parameter and the obtained operation inlet and equipment operating state to a steam generator water-level control main interface; carrying out functional attribute classification on the detected parameter and the obtained operation inlet and equipment operating state; setting the layout of the steam generator water-level control main interface according to a result of the functional attribute classification; and receiving a steam generator water-level control command and executing the corresponding steam generator water-level control operation. In the embodiment, after the information associated with the steam generator water-level control is functionally classified, the steam generator water-level control main interface is laid out, so that an operator can quickly obtain the parameter in an overall way and realize quick interference.

In conjunction with a pressurized water reactor (PWR) and a pressurizer configured to control pressure in the reactor pressure vessel, a decay heat removal system comprises a pressurized passive condenser, a turbine-driven pump connected to suction water from at least one water source into the reactor pressure vessel; and steam piping configured to deliver steam from the pressurizer to the turbine to operate the pump and to discharge the delivered steam into the pressurized passive condenser. The pump and turbine may be mounted on a common shaft via which the turbine drives the pump. The at least one water source may include a refueling water storage tank (RWST) and/or the pressurized passive condenser. A pressurizer power operated relief valve may control discharge of a portion of the delivered steam bypassing the turbine into the pressurized passive condenser to control pressure in the pressurizer.

A device separates a fluid mass flow in a nuclear plant. The device contains a primary end piece for conducting the fluid mass flow and a plurality of secondary end pieces for conducting a plurality of separate partial flows of the fluid mass flow. A number of separating elements is provided in the area within the primary end piece, and each of the partial areas defined by the separating element or the separating elements opens in a secondary end piece clearly assigned to the partial area.

Disclosed is an offshore, manned, scalable, modular, floating, moored, nuclear power generating plant and multipurpose platform. The present invention is comprised of a Main Plant Control Deck, Central Plant Deck, and submerged Reactor-Generator Deck(s) integrated into the structure of a Spar or Cell Spar Platform. The Reactor-Generator decks are comprised of a plurality of modular, Naval Nuclear Pressurized Water Reactor Modules. Electricity generated is transmitted via submarine High Voltage Direct Current Cables to shore. Ancillary, co-generated services, e.g. desalinated water, are transmitted to shore via submarine pipelines. Multipurpose Topside Decks house vessel command, crew, and any ancillary and co-generation equipment. The present invention, constructed in a multi-path manufacturing process, provides exceptional economic, environmental, sustainability, security, safety, and operational advantages over the current art of power generation.

A nuclear reactor instrumentation system and method, including a backup power source, a wireless transmitter, and various system sensors is configured to identify a loss of normal power to a nuclear reactor instrumentation system and cause power to be provided from the backup power source to the wireless transmitter in order to transmit data from nuclear reactor instrumentation sensors to a remote location via the wireless transmitter.

The Seafloor Power Station is one or more unmanned electric power generating Units (2) sending power to and operated from existing coastal sites by a manned facility (1) by connecting lines and hoses (3) delivering power to a grid by lines (4). Each Unit's hull (11) maintained in a vacuum, contains both nuclear steam and electricity generating systems. The hull functions as overpressure containment and as condenser in the event of a loss of coolant accident or other steam release. The Units operate submerged in very cold water, with depth set by remotely controlled vertical mooring systems, mounted on gravity mats (27). A Unit must be surfaced by its mooring system to refuel the reactor, an action both conspicuous and public, enabling international oversight of the fuel disposition.

A method for estimating a helium content of the stainless steel core shroud in a boiling water nuclear reactor includes, in an exemplary embodiment, determining a neutron fluence for predetermined areas of the reactor, and estimating a helium content of the stainless steel shroud at predetermined areas of the reactor using the following equation: C_He=1031*(1−e^{−b<sub2>j</sub2>*φ<sub2>j</sub2>}), where C_He is the helium concentration as atomic parts per billion of helium in the stainless steel shroud per weight parts per million of boron in the stainless steel shroud, b_j is a value between about 2.50 e⁻²¹ and about 5.00 e⁻²¹, φ_j is fluence expressed as neutrons per square centimeter, and subscript j denotes thermal fluence or fast fluence.