摘要:
A system and a method for removing and consolidating the spent fuel rods of a fuel assembly is disclosed herein. The sytem comprises a pushing assembly having a push rod for pushing a selected fuel rod out of a fuel assembly, a fuel assembly positioner including an elevator for conveniently positioning a fuel assembly within the spent fuel pool of a nuclear facility, a rod catching grid for preventing the pushed-out fuel rods from falling to the bottom of the pool and a transition cannister for funneling the rods into a consolidated arrangement within a storage cannister. In operation, the push rod is positioned over and engaged against the upper end of a fuel rod to be removed from the assembly. Thus engaged, the push rod is inserted through the cells in the grids of the fuel assembly that surround the selected fuel rod, thereby pushing it out of the fuel assembly. Thus the grid cells are used as an alignment means for the push rod during the rod-pushing operation.
摘要:
A vent system for controlling hydraulically actuated drive means for selectively moving pluralities of rod clusters respectively connected to the plurality of drive means between fully inserted positions within the lower barrel assembly of the vessel in telescoping relationship with fuel rod assemblies contained therein, and a fully withdrawn position. Each drive means responds to the reactor coolant fluid pressure and includes a leakage passage and an outlet channel through which a leakage flow may pass under control of the vent system, the latter comprising a valve arrangement, flow restrictors and a common orifice through which the outlet channels are selectively connected to essentially ambient pressure, for establishing a pressure differential within each drive means producing a net force for moving the drive rods and associated clusters to the withdrawn position at which the drive means mechanically latch the fully withdrawn clusters for mechanically supporting same in the fully withdrawn position. The valve arrangement may be selectively actuated to reestablish the pressure differential within each drive means thereby to raise the associated drive rods and release same from the mechanically latched positions, after which the valve arrangement is selectively operated to establish pressure equilibrium within the drive means to permit the corresponding drive rods and associated control rod clusters to fall by force of gravity to the fully inserted positions thereof. Display indications and control panel operation provide for operator sensing of the rod cluster positions and control of the valve arrangement.
摘要:
A top end support for rod guides disposed in closely spaced, parallel axial relationship within an inner barrel assembly of a pressurized water reactor vessel includes, in telescoping relationship, a generally cylindrical support having an end closure with a central aperture therein for receiving a downwardly depending extension from a lower calandria plate and a sleeve having an outer periphery corresponding in cross-section to that of said rod guide and affixed thereto at its lower end, the sleeve having an interior, generally cylindrical surface for receiving the cylindrical support in close engagement therein. The telescopingly engaged, generally cylindrical surfaces of the cylindrical support and the sleeve provide substantial area to function as a long-life wear couple. Both the end closure and the cylindrical sidewalls of the fixed cylindrical support and the interior surface of the sleeve are configured so as to correspond to the perimeter of flow holes disposed in a symmetrical array about the associated depending extension, to permit unimpeded passage therethrough of the core outlet flow.
摘要:
The hydraulic drive mechanism comprises an hydraulically actuated rod drive mechanism that cooperates with a pivotable latching mechanism. The pressurized reactor coolant is utilized to raise the drive rod into contact with and to pivot the latching mechanism so as to allow the drive rod to pass the latching mechanism. The pressure in the housing is then equalized which allows the drive rod to move downwardly into contact with the latching mechanism but remain in a raised position with respect to the reactor core. Once again, the reactor coolant pressure may be utilized to raise the drive rod and thus pivot the latching mechanism so that the drive rod passes above the latching mechanism. Again, the mechanism pressure can be equalized which allows the drive rod to fall and pass by the latching mechanism so that the drive rod approaches the reactor core.
摘要:
An apparatus and method are provided for replacing the existing lower internal components in a nuclear reactor vessel with new components. The alignment of the new lower internals to the pressure vessel and the existing upper internals is achieved by customizing the new lower internals on-site based on alignment measurements obtained by gages installed on the new core barrel and the existing upper core plate. The gages allow the custom machining of radial support keys on the lower portion of the new core barrel and the custom drilling of upper core plate alignment pin holes in the new core barrel.
摘要:
Modular neutron reflector assemblies removably insertable into the irregular space in a nuclear reactor between a generally cylindrical array of square fuel assemblies comprising the core and the cylindrical core barrel surrounding the core, include an elongated enclosure having a strongback adjacent the core barrel and flat plates adjacent the fuel assemblies. The strongback is thicker than the steel plates by an amount which results in the strongback and plates reaching approximately the same temperature to minimize thermal stresses despite the 8 to 20 times greater nuclear heating at the core side of the enclosure as opposed to that at the core barrel side. The enclosure is suspended by a single point mounting on the core barrel which permits vertical, radial, and circumferential expansion but a pin depending from the lower end of the enclosure slides in a vertical bore in the reactor lower core support plate to limit lateral movement while allowing unrestrained vertical expansion and contraction. A separately removable reflector unit in each enclosure comprises a bundle of closely packed stainless steel circular rods with smaller diameter rods inserted in the interstices between the larger rods to generate a 0.90-0.92% volume fraction of stainless steel while also providing a distributed array of small longitudinal passages for reactor coolant. Selected rods are suspended from a cover plate on the module with the remaining rods suspended from a horizontal plate which is in turn, suspended from the selected rods so that the rods are all free to expand and contract vertically.
摘要:
The mechanical spectral shift reactor comprises apparatus for inserting and withdrawing water displacer elements from the reactor core for selectively changing the water-moderator volume in the core thereby changing the reactivity of the core. The apparatus may include drive mechanisms for moving the displacer elements relative to the core and guide mechanisms for guiding the displacer rods through the reactor vessel. An array of tubes may be disposed between the guide mechanisms and the fuel assemblies for guidance and minimization of flow induced vibrations of the displacer elements.
摘要:
To preclude failure of components of control-rod assemblies or of unprotected control rods (WDRC's) a calandria is provided above the upper internals. The calandria includes hollow tubes through which the drive rods for the various control rods pass and which protect the drive rods. The guides for the control rods are closed except at the top so that the coolant flows vertically through the guides into the calandria. In the calandria, the coolant flows transversely to the hollow tubes and out through the outlet nozzle. The tubes have a mass and stiffness and strength such that they resist failure by reason of the transverse flow of the coolant to which they are subjected.
摘要:
The mechanical spectral shift reactor comprises a reactive core having fuel assemblies accommodating both water displacer elements and control rods for selectively changing the volume of water-moderator in the core. The fuel assemblies are arranged in alternating fashion so that one drive mechanism may move displacer elements in more than one fuel assembly without interfering with the movement of control rods or the corresponding control rod drive mechanisms.
摘要:
A radial neutron reflector is disclosed for a light water nuclear reactor. The irregular space between the core periphery and the core barrel surrounding the core is filled with a structure comprising material other than hydrogen such as zirconia or stainless steel so as to displace the reactor water coolant in this region. The structure is provided with appropriately sized flow holes to pass reactor coolant therethrough and to balance the pressure within the structure to substantially coincide with the axial pressure profile at the core periphery.