71 results about "Containment building" patented technology

Methods are disclosed for nondestructive testing and measuring the structural health of prestressed concrete structures, such as slabs, columns, girders, bridges, towers, elevated storage tanks, silos, cooling towers, wind power generation towers, liquefied gas storage tanks, nuclear power containment buildings, and the like. Measurements are made as the structure undergoes tensioning and detensioning operations. By measuring actual movements of cardinal points on the structure, in an absolute three-dimensional coordinate system, and comparing the measurements to a model—as tension on a tendon is changed—a margin of safety is assured. High accuracy measurements are made by electronic distance measurement (EDM) instruments over hundreds of meters, which yield coordinates of cardinal points with an uncertainty of the order of one part per million. The methods are proposed as possible alternatives to prior failures of post-tensioned concrete, including the Las Lomas Bridge, the Kapiolani Interchange On-Ramp, Turkey Point Unit 3 Nuclear Power Plant, and Crystal River Unit 3 Nuclear Power Plant. An extensive review of the most closely related prior arts is included.

The invention belongs to a device for spraying and cooling of the outer surface of a containment vessel in a passive mode, and particularly relates to the nuclear reactor containment vessel spraying and cooling device. The passive containment vessel spraying device comprises a safe spraying box, the safe spraying box is connected with an annular spraying header through a water transmission pipeline, the annular spraying header is arranged above a containment vessel dome, and a normally closed valve assembly is arranged between the water transmission pipeline and the annular spray header. The passive containment vessel spraying device has the advantages that the passive containment vessel spraying device is different from an active containment vessel interior spraying system of a conventional nuclear power plant and adopts an external spraying mode, does not need a safety-level emergency power supply and active components, and can realize short-term and long-term cooling of the containment vessel during superposition of a reactor loss-of-coolant accident or a main steam pipeline fracture accident with a station blackout accident and other superposition of multiple extreme accidents.

A reactor containment vessel of a boiling water reactor configured to contain a reactor pressure vessel. The reactor pressure vessel is connected to at least one main steam pipe which penetrates the reactor containment vessel at a main-steam-line penetration point. The main-steam-line penetration point is disposed on a first side of the reactor containment vessel. Distance between outer surface of the reactor pressure vessel and inner surface of the reactor containment vessel on the first side is longer than the distance on a second side which is opposite to the first side.

A wet filter for a nuclear reactor primary containment vent that employs an inclined manifold having a plurality of outlets that communicate through a first set of metal fiber filters submerged in a pool of water enclosed within a pressure vessel. A demister suspended above the pool of water to remove any entrained moisture in the filtered effluent before being passed through a second stage of higher density, dry, metal fiber filters connected to a second manifold that communicates with an outlet on the pressure vessel that is connected to an exhaust passage to the atmosphere.

The invention relates to a nuclear reactor containment cooling simulation system and method based on external spraying. The system comprises containment, experiment gas nozzle, a raw water high-level water tank, a variable-frequency spraying water pump, a spraying nozzle and a liquid storage tank, wherein the raw water high-level water tank, the variable-frequency spraying water pump, the spraying nozzle and the liquid storage tank are sequentially connected, the spraying nozzle is located right above the containment, and the experiment gas nozzle is located in the containment; a data collecting device and a mass spectrometer are arranged outside the containment, an inlet flowmeter, an inlet thermocouple, an inlet pressure sensor and an experiment gate valve are sequentially serially connected between the variable-frequency spraying water pump and the spraying nozzle; an outlet thermocouple and an outlet flowmeter are sequentially serially connected between the spraying nozzle and the liquid storage tank. Water is injected through the opening and closing of a water injection gate valve and the experiment gate valve, the spraying nozzle sprays water, and the features and rules of the internal thermal-hydraulic phenomena of the containment after the outside of the containment is sprayed according to obtained data. The nuclear reactor containment cooling simulation system is reasonable in design and widely applicable and provides technical and data support for the engineering construction and design transformation of advanced nuclear reactors of China.

The invention relates to a migration transfer characteristic test system of fragments of a reactor containment and a test method thereof. The system comprises a test segment module composed of a waterchannel, a rectifying grid, a filter screen and related equipment, a flow rate adjusting module composed of a water tank, a main water pump, an electric valve and related pipelines and instruments, acooling module composed of a cooling water pump, a heat exchanger, a cooling tower and related pipelines and instruments, a thermotechnical hydraulic parameter measuring module composed of a flowmeter, a temperature sensor, a pressure sensor and a liquidometer, an image collecting module composed of a high-speed camera, a local area network computer and related image processing software, a flow field information collection module composed of PIV equipment, a local area network computer and related flow field processing software and a remote control module composed of a programmable logic controller, a water pump, an electric valve and related equipment. The system simulates a ground water flow velocity field of the containment accurately after loss of coolant accident and acquires characteristic parameters of different fragments migrating in water.

Disclosed herein is a water-air combined passive feed water cooling apparatus including a water cooling heat exchanger connected to the inside of a containment building to cool down heat of a steam generator using a water cooling method, a cooling tank including the water cooling heat exchanger therein and storing cooling water condensing main steam generated by the steam generator, an evaporative steam pipe connected to the cooling tank, the evaporative steam pipe, into which steam of the cooling water generated by the water cooling heat exchanger in the cooling tank flows, an air cooling heat exchanger connected to the evaporative steam pipe and cooling down and liquefying the steam flowing into the evaporative steam pipe, and a condensed water collecting pipe for refilling the cooling tank with the steam liquefied by the air cooling heat exchanger.

The invention provides steel for a gate of extra-thick nuclear reactor containment, and a manufacturing method thereof. The components of a steel plate include, by weight percentage, 0.08-0.15% of C,0.25-0.50% of Si, 0.90-1.50% of Mn, P <= 0.01%, S which is less than or equal to 0.005%, 0.30-0.60% of Ni, 0.10-0.30% of Cr, 0.10-0.30% of Mo, 0.01-0.05% of V, 0.01-0.05% of Nb, 0.01-0.03% of Al, andNb and V which are less than or equal to 0.08%, with the balance being Fe and inevitable impurities. The manufacturing method includes steel ingot cogging, intermediate billet rolling and heat treatment. The steel plate can be guaranteed to have high intensity while having uniform and stable low-temperature toughness, and the steel plate can still have good comprehensive properties after simulatedwelding and heat treatment.

Apparatus for amplifying low level signals within a nuclear plant's containment building, derived from the ex-core nuclear instrumentation system. The system employs vacuum micro-electronic devices in place of conventional pre-amplifier assemblies to position the pre-amplifier assemblies closer to and within the vicinity of the ex-core detector outputs.

The invention relates to a passive containment cooling system, which includes a top water tank (5) disposed outside a containment and a spiral coil water cooled wall (1) arranged in the containment, one end of the spiral coil water cooled wall (1) is connected to the top water tank (5) through a natural circulation inlet pipeline (3), the other end of the spiral coil water cooled wall (1) is in connection with the top water tank (5) through a natural circulation outlet pipeline (2), the spiral coil water cooled wall (1) is disposed in a containment dome (4) area and includes one or more spiral coils. The containment cooling system provided by the invention has the advantages of few containment penetration pieces, large heat exchange area, high heat exchange efficiency and good seismic performance, and also has a simple structure, thus providing higher inherent safety for nuclear reactor containments.

A residual heat removal system for a nuclear power plant. The residual heat removal system for a nuclear power plant may include an air duct provided on an outside of a reactor containment building, a heat exchanger disposed on an inside of the air duct, a first pipe to transfer, to the heat exchanger, steam generated in a steam generator disposed on an inside of the reactor containment building, and second pipe to transfer, to the steam generator, water condensation that is cooled and condensed in the heat exchanger, wherein the heat exchanger is air-cooled using outside air flowing inside of the air duct.

The present invention discloses a passive cooling system of a containment building, to which a plate-type heat exchanger is applied. A passive cooling system of a containment building comprises: a containment building; a plate-type heat exchanger provided to at least one of the inside and the outside of the containment building and comprising channels respectively provided to the both sides of a plate so as to be arranged dividedly from each other such that the plate-type heat exchanger carries out mutual heat exchange between the internal atmosphere of the containment building and a heat exchange fluid while maintaining a pressure boundary; and a pipe connected to the plate-type heat exchanger by penetrating the containment building so as to form the path of the internal atmosphere of the containment building or the heat exchange fluid.

This invention provides a method for stabilization of paint residue subject to acid and water leaching tests or leach conditions by addition of stabilizing agents within an OSHA containment building or collection device such that leaching of lead is inhibited to desired levels. The resultant waste after stabilization is deemed suitable for on-site reuse, off-site reuse or disposal as RCRA non-hazardous waste.

The invention discloses automatic detection system and method for hollowing in a steel lining of a nuclear reactor containment. The system includes a wall-climbing robot and an intelligent terminal, which are connected to each other. A knocking apparatus and a sound collection module are arranged on the wall-climbing robot. The wall-climbing robot climbs all over on the inner wall of the nuclear reactor containment and knocks the inner wall by means of the knocking apparatus, wherein the knocking sound information is collected by the sound collection module in real time and is sent to the intelligent terminal; the intelligent terminal then controls the wall-climbing robot to move on the inner wall of the nuclear reactor containment and receives the sound information and detects whether hollowing exists or not between the steel lining and the inner wall according to the sound information. The system and method can automatically detect the swelling in the steel lining of the nuclear reactor containment and are reduced in detection cost and improved in detection efficiency and quality, and are extensively applied to the field of auto-detection computing.

The invention provides an optimal method for stabilization of heavy metal bearing paint residue subject to acid and water leaching tests or leach conditions by addition of environment safe, worker safe, multi-media compatible, non-separating, non-embedding, stabilizing agent and optional complexing agent(s) to the blast media, thus allowing for pre-blending of stabilizer and blast media and field production of a uniform and steady state stabilizer within media for stabilization outside or within an OSHA containment building or collection device, such that leaching of heavy metals such as lead are inhibited to desired levels. The resultant stabilized paint residue and spent blast media mixture is suitable for on-site reuse, off-site reuse, or disposal as RCRA non-hazardous waste.

The invention relates to a sleeve combined type embedded part for a rebar dense part of a high-temperature gas-cooled reactor containment building, and belongs to the technical field of nuclear powerengineering construction. The sleeve combined type embedded part comprises an anchor plate, a twistable anchor rib and a threaded connection sleeve. An internal thread is machined in the threaded connection sleeve. One end of the threaded connection sleeve is directly connected to the inner surface of the anchor plate through welding. An external thread is machined in one end of the twistable anchor rib. The end, with the external thread, of the twistable anchor rib is screwed into the internal thread of one end of the threaded connection sleeve and screwed down to form threaded connection. Bymeans of the sleeve combined type embedded part, the problem that conventional anchor plate-anchor rib welded type embedded parts especially some large embedded parts of a rebar dense part of a containment building are difficult to install in place is successfully solved, the installation quality and construction efficiency of the embedded part are greatly improved, the construction cycle of thecontainment building is shortened, and the sleeve combined type embedded part has application and popularization value for designing and installing of embedded parts of rebar dense parts in other nuclear reactor types and other engineering fields.

A nuclear reactor containment system including a nuclear reactor and a container enclosing the nuclear reactor. The container includes a number of heat removal systems each having an active state and an inactive state, wherein the heat removal systems dissipate heat from the container more efficiently in the active state than in the inactive state, and wherein the heat removal systems are structured to switch from the inactive state to the active state based on a temperature of the container.

A coolant recirculation system of a nuclear power plant is provided that may include: a reactor vessel configured to accommodate a reactor core and a reactor coolant therein; a steam generator configured to transfer a gas, converted from a liquid phase to a gaseous phase by exchanging heat with the reactor coolant, to a turbine system; a pressurizer configured to control pressure of the reactor coolant in the reactor vessel; a primary system pressure reducing valve located above the pressurizer and configured to open at a predetermined pressure to discharge the reactor coolant into a containment building for rapid depressurization; and a moisture separator connected to the primary system pressure reducing valve to separate moisture. The moisture separator may separate the reactor coolant into a gaseous phase and a liquid phase. Then, the liquid phase reactor coolant may be returned to the reactor vessel to be recirculated.

The passive system is suitable for prefabrication and installation as a variable volume unit enclosing industrial components, systems, buildings and structures at operating light water reactors without interference with the design basis operations and performance of the buildings, structures, systems and components enclosed. This invention removes the energy from residual heat and hydrogen generation accumulated inside the containment buildings and spent fuel pool buildings challenged by over temperature and over pressure during severe accidents, while encapsulating the radioactive atmospheric fallout, condensing steam by heat exchange with the atmosphere and retaining the resulting water coolant. This invention also encapsulates design basis accidents releases such as the release of radioactive steam through hardened venting systems to the atmosphere, and the release of radioactive steam through containment bypass systems to the atmosphere.