摘要:
A shroud for a nuclear reactor is described. In one embodiment, the shroud includes first and second shroud sections, and each shroud section includes a substantially cylindrical main body having a first end and a second end. With respect to each shroud section, a flange is located at the main body first end, and the flange has a plurality of bolt openings therein and a plurality of scalloped regions. The first shroud section is welded to the second shroud section, and at least some of the bolt openings in the first shroud section flange align with respective bolt openings in the second shroud section flange. In the event that the onset of inter-granular stress corrosion cracking is ever detected in the weld between the shroud section, bolts are inserted through bolt openings in the first shroud section flange and through aligned bolt openings the second shroud section flange. Each bolt, in one embodiment, has a shank section and first and second threaded end sections. Nuts are threadedly engaged to the threaded end sections and tightened against the respective flanges.
摘要:
A tool for installing and torquing a tensioning nut onto a tie rod of a shroud repair apparatus. The nut torquing tool has a socket for coupling with the tensioning nut and an adaptor for coupling with a manually operated handling pole, wherein the axis of rotation of the socket is radially displaced relative to the axis of rotation of the adaptor. The respective shafts connected to the socket and adaptor are coupled by means of a pair of sprockets and a chain which convert rotation of the adaptor into rotation of the socket. The distance between the sprockets can be adjusted to tension the chain. The handling pole adaptor is connected to a drive shaft by way of a universal joint, a torque limiter and a torque multiplier. Incorporation of a torque multiplier facilitates installation and torquing of the tensioning nut in a single operation using a lightweight handling pole.
摘要:
A remotely operated drilling tool is configured to produce holes in a core shroud support plate inside of a nuclear reactor vessel. The tool includes a support base that is securely mounted directly above the location where the hole will be formed. In a first operation, a drilling tool is secured to the support base and drills a hole through about 90% of the shroud support plate. The drilling tool includes chip capturing structure to prevent chip created by the machining process from contaminating the water in the reactor vessel. After about 90% of the hole is drilled with the drilling tool, an EDM tool is secured to the support base to machine the remainder of the hole using an EDM process. The EDM tool includes structure for machining the remainder of the hole, removing the slug from the hole, and performing a spotface on the underside of the shroud support plate. The underwater drilling tool is capable of producing high quality holes faster and more efficiently than the current EDM process, while maintaining control of all foreign material, minimizing the deleterious effects on the material being drilled, and reducing the risk associated with poor tool reliability and breakage.
摘要:
A tool for installing a support member which must be rotated into a horizontal position in the downcomer annulus of a boiling water reactor by remote manipulation. The support member may, for example, be a midsupport for damping flow-induced vibrations in a vertical restraint tie rod. The tool includes a rigid holder for holding the support member and a threaded pivot for coupling with the threaded end of a cable. The pivot can swing relative to the holder between first and second angular positions separated by 90.degree.. The support member is held in the holder by a pair of channels formed on the holder and a set screw which threads in the holder and enters a bore formed in the support member. After the support member has been secured to the holder, the holder is coupled to the end of the cable via the pivot. The support member is lowered in the downcomer annulus in a vertical position. When the support member reaches the installation elevation, the support member is pivoted into a horizontal position for engagement with the tie rod. The tool is disengaged from the installed support member by remote manipulation of the set screw.
摘要:
In a boiling water reactor having a core shroud disposed within a reactor vessel and a plurality of tie rods installed between vertically spaced sites on the core shroud as part of a core shroud repair, a method of measuring tie rod preload after installation includes the steps of lowering a tool into the reactor vessel from a remote location positioned externally of the reactor vessel, attaching the tool to an upper portion of a tie rod, using the tool to apply a tensile load along a longitudinal axis of the tie rod, measuring the tensile load applied to the tie rod, measuring axial displacement of the tie rod in response to the applied tensile load, plotting the applied load versus the axial displacement measured, and identifying a change in slope on the load-displacement plot occurring at a load corresponding to the tie rod preload.
摘要:
In a pressure vessel of a nuclear reactor containing a core assembly enclosed within a core shroud, the core shroud spaced radially inwardly of a side wall of the pressure vessel with an annular pump deck located in an annular radial space between the core shroud and the side wall of the pressure vessel, the improvement wherein the shroud is removably secured to an annular support leg extending upwardly from the bottom of the pressure vessel; and further wherein the annular pump deck is provided in the form of a plurality of removable segments.
摘要:
During a shutdown of the reactor, a device for partially closing off (27) the openings (26) of the reinforcements (6) located below the upper reinforcement (6a) is introduced through the opening (25) of the upper reinforcement (6a) of the partitioning of the core of the reactor. The closing off devices (27) remaining in position in the partitioning of the reactor after restarting thereof permit the increase and regulation of the head loss of the cooling water circulating in the annular space (7) around the partitioning (5) of the core. The closing-off device may consist of a rod (27) engaged in a set of openings (26) of the reinforcements (6) aligned along a vertical direction.
摘要:
A modular lining for adapting the containment to the core of a pressurized water nuclear reactor, consisting of juxtaposed modular blocks (5) placed between the core containment (1) and the outer surface of the core (3). Arranged between the adjacent faces of the blocks (5), there are thin packing pieces (8) maintaining a certain gap between the undrilled solid blocks (5). The blocks (5) are fixed non-contiguously to the core containment (1) by screw devices (10) cooled by water circulation. The invention applies in particular to pressurized water nuclear reactors of improved efficiency and with a varying neutron spectrum.
摘要:
A fast breeder reactor has a nuclear reactor container filled with a liquid metal, a reactor core disposed within the nuclear reactor container, and a first supporting structural member which is mounted to the nuclear reactor container such as to support the reactor core. The fast breeder reactor is provided with a cylindrical structural member which surrounds the periphery of the reactor core such as to define an annular gap between the cylindrical structural member and the reactor core for allowing the liquid metal to exist therein, the cylindrical structural member being mounted to the nuclear reactor container by means of a second supporting structural member. The inertial resisting force produced when the liquid metal existing in the annular gap will flow out from the annular gap in response to the vibration of the reactor core acts such as to suppress the vibration of the reactor core, thereby allowing an improvement in the anti-vibration properties of the fast breeder reactor.
摘要:
A nuclear reactor with juxtaposed prismatic fuel assemblies cooled by the flow of a liquid in a cylindrical jacket. A partitioning of the core between the peripheral assemblies and the jacket is constituted by rods parallel to the assemblies, guided laterally by bracing plates fast to the jacket in which the rods are free to slide longitudinally.