102results about "Plant pumping arrangements" patented technology

An apparatus for reinforcing a jet pump riser includes: an elbow upper clamp for covering a riser elbow coupled to a thermal sleeve from an upper side thereof; an elbow lower clamping member for clamping the riser elbow from a lower side thereof; an elbow vertical portion clamping member for covering a vertical portion of the riser elbow; and an elbow horizontal portion clamping member for covering a horizontal portion of the riser elbow. These members are disposed in different orientations with respect to the elbow upper clamp so as to fix the thermal sleeve, the riser elbow and the riser pipe.

An apparatus for reinforcing a jet pump riser includes: an elbow upper clamp for covering a riser elbow coupled to a thermal sleeve from an upper side thereof; an elbow lower clamping member for clamping the riser elbow from a lower side thereof; an elbow vertical portion clamping member for covering a vertical portion of the riser elbow; and an elbow horizontal portion clamping member for covering a horizontal portion of the riser elbow. These members are disposed in different orientations with respect to the elbow upper clamp so as to fix the thermal sleeve, the riser elbow and the riser pipe.

The invention discloses a shaft sealing water injection system of a main pump of a nuclear power station. The shaft sealing water injection system comprises an injection pump, a high-pressure cooler, a hydrocyclone, valves and a main connecting pipeline that are arranged at the exterior of the main pump, as well as an auxiliary pump and an internal runner that arranged in the main pump; the internal runner of the main pump is connected with an external runner of the main pump through a shaft sealing water injection hole and a high temperature water drainage hole that are formed in a main flange; and the injection pump, the high-pressure cooler and the hydrocyclone are sequentially arranged on the main connecting pipeline. The shaft sealing water injection system further comprises a bypass pipeline connected with the injection pump, the high-pressure cooler and the hydrocyclone in parallel; the main connecting pipeline is provided with a normally open main pipeline isolating valve at each of the two ends of a parallel connection section connected with the bypass pipeline in parallel; and the bypass pipeline allows low temperature upward filling water of a RCV system to be able to bypass the injection pump, the high-pressure cooler and the hydrocyclone and to directly enter the shaft sealing water injection hole of the main flange. Compared with the prior art, through redundancy design, and optimization of a system structure and control, the safety and the reliability of system operation and the maintainability of the shaft sealing water injection system are ensured.

An auxiliary system for cooling a spent nuclear fuel pool through a submersible heat exchanger to be located within the pool. In each train or installation, a single loop or series of loops of cooling fluid (e.g., sea water or service water) is circulated. The system is modular, readily and easily installed during an emergency and can be self operating with its own power source. Multiple trains may be used in parallel in order to accomplish the required degree of spent fuel pool cooling required.

A method and apparatus for providing an alternative remote spent fuel pool cooling system for the spent fuel pool. The cooling system is operated to cool the spent fuel pool in the event of a plant accident when normal plant electricity is not available for the conventional fuel pool cooling and cleanup system, or when the integrity of the spent fuel has been jeopardized. The cooling system is operated and controlled from a remote location, which is ideal during a plant emergency.

The invention relates to a passive advanced pressurized water reactor coolant pump installation technology. The passive advanced pressurized water reactor coolant pump installation technology is characterized in that a main pump occasional passage is provided; before a main pump is introduced to a nuclear island workshop, butt joint between a flat car transporting the main pump and the main pump occasional passage is completed; a draw gear is used to introduce a main pump / transport towing bracket assembly embarked on a mobile device to the nuclear island workshop; during the drawing process, a tail slipping device is used to prevent the moving speed becoming too fast, and then the main pump is moved to a turnover initial position; a ring crane hook is lifted and coordinates with moving of the mobile device so as to turnover the main pump, and at the same time, a tow rope of the tail slipping device is adjusted; the main pump is lifted to a steam generator cavity, and is located in a main pump installation mechanical device; a suction adapter in a pump housing completes the installation work before installation of the main pump; the main pump installation mechanical device is utilized to provide moving, positioning, adjusting and lifting of the main pump; and a sealing ring at the upper part of the main pump and the pump housing directly utilize the welded sealing technology to realize prevention of leakage during the operating process.

Disclosed is a nuclear power plant which drives a Stirling engine by means of heat generated in nuclear power plant safety systems during an accident, uses the resulting power directly or generates electric power so as to supply the power to the safety systems, and thus can improve economic efficiency as well as the reliability of safety systems, such as a passive safety system, by operating the safety systems without an emergency diesel generator or external electric power.

A component cooling water system for a nuclear power plant. In one embodiment, the system includes an inner containment vessel housing a nuclear reactor and an outer containment enclosure structure. An annular water reservoir is formed between the containment vessel and containment enclosure structure which provides a heat sink for dissipating thermal energy. A shell-less heat exchanger is provided having an exposed tube bundle immersed in water held within the annular water reservoir. Component cooling water from the plant flows through the tube bundle and is cooled by transferring heat to the annular water reservoir. In one non-limiting embodiment, the tube bundle may be U-shaped.

The invention relates to a method of repairing the labyrinth seal of a diffuser in a primary pump, the diffuser being of the type comprising a peripheral skirt and a circular end wall having an orifice provided with the labyrinth seal. The method consists in making a bore in the circular end wall having a diameter greater than that of the orifice, in reducing the thickness of the remaining portion of the end wall, in forming a chamfer on the edge of the bore, in positioning a replacement part in said bore, the replacement part including a central orifice and a chamfer on its own peripheral edge, in making a bead of welding between the chamfers, and in making a new labyrinth seal in the central orifice of the replacement part.

A system and a method for injecting hydrogen into Boiling Water Reactor (BWR) reactor support systems in operation during reactor startup and / or shutdown to mitigate Inter-Granular Stress Corrosion Cracking (IGSCC). The system may provide hydrogen at variable pressures (including relatively higher pressures) that match changing operating pressures of the reactor supports systems as the reactor cycles through startup and shutdown modes.

The present invention relates to filters used to remove debris from water being sucked into a piping system. It has particular application for use in nuclear power plants, which, after a loss of coolant accident, must pump cooling water back into the reactor core from a collection sump. This water may contain various types of debris that must be removed before the water is sent back into the reactor cooling system. Filtering of the debris is realized with the component known as “strainers”. There are restrictions on the space available for installing strainers. The vaned filtering element, for example a vaned fin, of the present invention is designed to reduce the space required for strainer installation by increasing strainer surface area per unit volume, while maximizing the quantity of debris that can be filtered from the water.

A nuclear steam supply system having a shutdown system for removing residual decay heat generated by a nuclear fuel core. The steam supply system may utilize gravity-driven primary coolant circulation through hydraulic-ally interconnected reactor and steam generating vessels forming the steam supply system. The shutdown system may comprise primary and secondary coolant systems. The primary coolant cooling system may include a jet pump comprising an injection nozzle disposed inside the steam generating vessel A portion of the circulating primary coolant is extracted, pressurized and returned to the steam generating vessel to induce coolant circulation under reactor shutdown conditions. The extracted primary coolant may further be cooled before return to the steam generating vessel in some operating modes. The secondary coolant cooling system includes a pumped and cooled flow circuit operating to circulate and cool the secondary coolant, which in tun extracts heat from and cools the primary coolant.