40 results about "Core shroud" patented technology

In a core-shroud bicomponent fiber, which exhibits a core and a shroud at least partially enveloping the core, an elevated abrasion behavior, a low compaction under exposure to temperature and pressure and a high strength of the fibers is achieved by having the shroud consist of 45-98% w/w of a first polyamide having a melting point exceeding 280° C., and 2-20% w/w of a layer silicate.

A heavy radial neutron reflector for a pressurized water reactor that employs elongated lengths of round bar stock closely packed in either a triangular or rectangular array extending between former plates of a core shroud between the core barrel and the baffle plates which outline the periphery of the reactor core and are formed in axial and circumferential modules. Flow channels are formed in the long gaps between the adjacent round bar stock that communicates cooling water that enters through the core barrel at the top of the shroud and flows down through openings in the former plates to the bottom of the neutron reflector where it exits through a lower baffle orifice to join other cooling water flowing up through the lower core support plate.

The present invention provides a boiling water reactor nuclear power plant in which a reactor core support plate, upper grid plate, and a reactor core consisting of fuel assemblies supported by these plates are provided in the inner base portion of a nuclear reactor pressure vessel. Control rod guide tubes and a reactor core shroud are positioned over the upper grid plate, and a control rod drive mechanism is provided further above same, whereby the control rods can be inserted from above the reactor core, and natural circulation of cooling water inside the reactor can be achieved by means of a chimney effect of the control rod guide tubes. According to the above structure, there can be provided a compact and economical nuclear power plant.

This invention generally concerns robotic systems and is particularly concerned with improved apparatus and methods for remotely inspecting, modifying or repairing a core shroud in a nuclear reactor. The apparatus of the invention includes a partial upper track which horizontally movable along the core shroud, a head and frame assembly which is horizontally movable along the partial upper track, a lower track which is connected to the head and frame assembly and is horizontally movable along the core shroud, and a carriage and arm assembly which extends downward into an annulus formed by the reactor pressure vessel and the core shroud, wherein the arm includes at least one sensor for inspecting the core shroud.

An alignment system that employs jacking block assemblies and alignment posts around the periphery of the top plate of a nuclear reactor lower internals core shroud to align an upper core plate with the lower internals and the core shroud with the core barrel. The distal ends of the alignment posts are chamfered and are closely received within notches machined in the upper core plate at spaced locations around the outer circumference of the upper core plate. The jacking block assemblies are used to center the core shroud in the core barrel and the alignment posts assure the proper orientation of the upper core plate. The alignment posts may alternately be formed in the upper core plate and the notches may be formed in top plate.

The invention belongs to the technical field of manufacturing and processing of nuclear power reactor internal components, and discloses a welding and clamping device for a reactor core shroud assembly, which includes an inner support assembly, an outer hoop assembly and a roller assembly. Inner support of the section, each inner support is provided with a positioning layer and a top tight layer, the support assembly is arranged inside the core shroud assembly, and the outer hoop assembly includes several outer hoops, and each outer hoop is provided with a universal Jacking parts, the outer hoop assembly is arranged on the periphery of the core shroud assembly, the top tight layer of the inner support assembly and the universal jacking piece of the outer hoop assembly fix the core shroud as a whole, and the roller assembly includes rollers and The roller frame is provided with rollers at both ends of the core shroud, and the roller assembly makes the core shroud rotate and displace on the roller frame. The invention also discloses a clamp welding method. The invention realizes one-time clamping and multiple welding of the core shroud, and provides sufficient rigid support for deformation after welding.

The tie rod repair apparatus includes a tie rod secured at its upper end to the shroud flange at the top of the shroud. The lower end of the tie rod passes through an opening in the shroud support plate without imposing a load on the plate. The lower end of the tie rod is anchored to the lower end of the core shroud support cylinder such that the compressive load path exerted by the tie rod to restrain the cracked shroud passes directly through the shroud support cylinder and the assembly of shroud cylinders bypassing the shroud support plate.

The invention discloses a novel nature cycle cooling lead-based fast reactor. The novel nature cycle cooling lead-based fast reactor at least includes: a core, a main container, a core shroud, a heatpool, a cool pool, a main heat exchanger and a reactor top cover. The main container is a circular column metal container, the two ends of the main container are sealed; the core shroud is arranged inthe main container, the inner space of the main container is divided into the heat pool and cool pool; at least one part of the core shroud has a circular column metal plate with a taper curved surface, the core is arranged at the bottom of the heat pool of the main container, the height difference is existed between the core and the main heat exchanger, the main heat exchanger is connected withthe heat pool and cool pool, and the nature circulation canal of the cooling agent is formed by the main heat exchanger, cool pool and heat pool. The nature cycle capability of the first loop coolingagent can be enhanced, and the security and economy of the nature cycle cooling lead-based fast reactor are effectively improved.

The invention discloses a heat treatment method of a thorium-based fused salt main container and a core shroud. The method comprises the following steps of S1, heat treatment of the main container, specifically, the main container is of a vertical structure to be subjected to heat treatment, a bottom board is a carbon steel or low-alloy steel thick board and horizontally arranged on a furnace bodybearing point inside the furnace, and a placement plane of the main controller is provided; and S2, heat treatment of the core shroud, specifically, the core shroud is of a vertical structure to be subjected to heat treatment, the bottom board and a partition board are horizontally arranged on the furnace body bearing point inside the furnace, and a placement plane and an isolation effect of thecore shroud are provided. By the adoption of the heat treatment method of the thorium-based fused salt main container and the core shroud, the precision requirements for size changes in the heat treatment process of equipment can be effectively ensured, the heat treatment cost is reduced, the equipment which is subjected to heat treatment and is good in performance, stable in quality and high in precision is obtained, the manufacturing requirements of the thorium-based fused salt main container and the core shroud are met, and the service life of the equipment is prolonged.

The invention discloses a preparation method of an ultra-large integral stainless steel reactor core shroud member of a nuclear power plant, which comprises the following steps of: establishing a three-dimensional model of an ultra-large integral stainless steel reactor core shroud member of a nuclear power plant, and segmenting, blocking and layering the model in the axial direction; machining a stainless steel reactor core shroud structure layer by layer through the laser cladding forming technology, so as to complete machining of one stainless steel reactor core shroud structure; machining stainless steel reactor core shroud structures one by one, so as to complete machining of one section of stainless steel reactor core shroud structures; machining stainless steel reactor core shroud structures section by section, so as to complete machining of the stainless steel reactor core shroud structure on one side; and machining a second-side stainless steel reactor core shroud structure on the symmetric surface of a substrate forming the stainless steel reactor core shroud structure on one side, and finally forming an ultra-large integral stainless steel reactor core shroud structure of a nuclear power station. According to the preparation method provided by the invention, the reactor core shroud structure with excellent mechanical properties is integrally formed through a laser cladding forming technology, the material utilization rate is high, and the machining period is short.

The invention relates to the technical field of welding processes, in particular to a welding method of a reactor core shroud assembly, which comprises the following steps: forming a first groove surface and a second groove surface at two ends of a first folded plate, forming a third groove surface and a fourth groove surface at two ends of a second folded plate, and alternately connecting a plurality of processed first folded plates and second folded plates to form a barrel; due to the fact that the second groove face and the fourth groove face at the same connecting position are in butt joint to form the backing welding groove, the first groove face and the third groove face are in butt joint to form the TIG welding groove, the backing welding groove can be used for backing welding of the first folded plate and the second folded plate, and the premise is provided for the first folded plate and the second folded plate to achieve stability and meet the welding precision requirement through TIG welding. By means of TIG welding of the longitudinal weld joints, automatic welding of the longitudinal weld joints of the reactor core shroud assembly can be achieved, the welding efficiency is guaranteed, and meanwhile the welding cost of the reactor core shroud assembly can be effectively reduced.