摘要:
In a nuclear fuel rod assembly including a plurality of fuel rods and at least one water rod held together in a bundle, and wherein end plugs at the lower ends of the fuel rods and the at least one water rod engage a lower tie plate, an improvement wherein the end plug at the lower end of the at least one water rod is hollow and includes a multi-diameter flow metering bore for regulating coolant flow into the water rod.
摘要:
A control rod includes four panels in cruciform section each containing a plurality of absorber tubes. The absorber tubes are mounted between upper and lower mounting structures having generally T-shaped slots opening toward one another. The absorber tubes have generally T-shaped end plugs for reception in the slots. The slots and end plugs are configured to permit limited axial movement of each absorber tube relative to the control rod and to adjacent tubes. The absorber tubes are maintained in tension during all nuclear operations including during a scram.
摘要:
A fuel assembly for a nuclear reactor vessel includes a plurality of fuel rods, at least one coolant rod, a lower tie plate supporting the fuel rods and coolant rod, and a channel surrounding the fuel rods, coolant rod and tie plate. The lower tie plate is supported by the channel such that the channel carries a load of the fuel assembly. In one aspect of the invention, an upper tie plate includes two spring loaded latch pins engageable with corresponding apertures in the channel. A transition member supports the lower tie plate and is rigidly secured to the channel. Thus, when lifting the fuel assembly from the reactor, the channel bears the load of the fuel assembly. End gussets or clips are welded to the channel and inserted into the transition member, which serve as a secondary support for the transition member in the event that its primary connection to the channel fails. A channel guide member is secured to the, upper tie plate and includes two ears that are received in ear apertures in the channel. The channel guide and ears thus provide a redundant attachment between the tie plate and the channel in the event that the spring loaded latch pins fail. If it is desired to remove the fuel bundle from the channel, the upper tie plate is released from the assembly by detaching the guide member and releasing the spring loaded latch pins. The bundle can then be removed from the channel by attaching a grapple head to the coolant rod ends, which are specially shaped to facilitate an attachment tool.
摘要:
In a boiling water reactor fuel bundle, a three dimensional debris catching grid construction is placed within the flow volume defined by the lower tie plate assembly between the inlet nozzle and upper fuel rod supporting grid. A perforated plate is utilized having round holes as small consistent with the prevention of inadvertent closure due crudding and a hole pitch consistent with mechanical integrity requirements. The perforated plate is placed in a three dimensional construction such as a dome, cylinder, pyramid, inverted pyramid or corrugated construction spanning the flow volume of the lower tie plate assembly. As a consequence of this three dimensional grid construction, the total flow through area of the perforations in the metal plate does not introduce appreciable pressure drop in the lower tie plate assembly between the inlet nozzle and the rod supporting grid. Fluid movement at the debris restraining holes of the grid construction has a low flow velocity and a change in flow direction before passing through the holes to discourage debris from finding its way through the grid holes. Finally, it is possible to incorporate debris traps within the flow volume of the lower tie plate assembly that can cause trapping and subsequent removal of trapped debris upon fuel bundle replacement. A double corrugated plate having large holes in the lower plate and smaller holes in the upper plate is utilized to trap debris.
摘要:
In a boiling water reactor fuel bundle, a three dimensional debris catching grid construction is placed within the flow volume defined by the lower tie plate assembly between the inlet nozzle and upper fuel rod supporting grid. A perforated plate is utilized having round holes as small consistent with the prevention of inadvertent closure due crudding and a hole pitch consistent with mechanical integrity requirements. The perforated plate is placed in a three dimensional construction such as a dome, cylinder, pyramid, inverted pyramid or corrugated construction spanning the flow volume of the lower tie plate assembly. As a consequence of this three dimensional grid construction, the total flow through area of the perforations in the metal plate does not introduce appreciable pressure drop in the lower tie plate assembly between the inlet nozzle and the rod supporting grid. Fluid movement at the debris restraining holes of the grid construction has a low flow velocity and a change in flow direction before passing through the holes to discourage debris from finding its way through the grid holes. Finally, it is possible to incorporate debris traps within the flow volume of the lower tie plate assembly that can cause trapping and subsequent removal of trapped debris upon fuel bundle replacement.
摘要:
A latch pin assembly is configured to enable selective engagement with at least one of the fuel assembly channel and the coolant rod such that the fuel assembly channel and the coolant rod can be selectively utilized to support the fuel assembly load, thereby eliminating the need for fuel tie rods. The latch pin assembly includes a latch pin selectively engageable with the fuel assembly channel and the coolant rod, and an anchoring assembly cooperating with the latch pin, wherein the anchoring assembly anchors the latch pin in a selected position such that the latch pin engages at least one of the fuel assembly channel and the coolant rod. The latch pin may be alternatively engageable with the fuel assembly channel and the coolant rod or simultaneously engageable with the fuel assembly channel and the coolant rod. With this arrangement, the bail handle can be used both to remove the entire assembly including the fuel assembly channel from the reactor vessel or to remove only the fuel bundle from the reactor vessel, leaving the fuel assembly channel in place.
摘要:
A fuel assembly for a nuclear reactor vessel includes a plurality of fuel rods, at least one coolant rod, a lower tie plate supporting the fuel rods and coolant rod, and a channel surrounding the fuel rods, coolant rod and tie plate. The lower tie plate is supported by the channel such that the channel carries a load of the fuel assembly. In one aspect of the invention, a conventional upper tie plate is removed and a handle assembly is provided that includes two spring loaded latch pins engageable with corresponding apertures in the channel. A transition member supports the lower tie plate and is rigidly secured to the channel. Thus, when lifting the fuel assembly from the reactor, the channel bears the load of the fuel assembly. If it is desired to remove the fuel bundle from the channel, the handle assembly is released from the assembly by releasing the latch pins. The bundle can then be removed from the channel by attaching a grapple head to the coolant rod ends, which are specially shaped to facilitate an attachment tool.
摘要:
A multi-fiber fiber optic ferrule comprising a ferrule body, at least one optically functional optical fiber received within at least one optical fiber bore defined by the ferrule body, and at least one optically non-functional guard fiber received within at least one guard fiber bore defined by the ferrule body. A multi-fiber ferrule defining at least one optical fiber bore opening through a front face, at least one optically functional optical fiber received within the ferrule and maintained within the at least one optical fiber bore, at least one guard fiber bore opening through the front face, and at least one optically non-functional guard fiber received within the at least one guard fiber bore.
摘要:
In a nuclear reactor fuel bundle assembly having a plurality of fuel rods and a non-round water rod extending between upper and lower tie plates, and having at least one fuel rod spacer located along the non-round water rod, an improvement which includes cooperating components on the fuel rod spacer and on the water rod for permitting movement of the spacer along the water rod to a desired axial location and for thereafter preventing further axial movement of the spacer in at least one of two opposite axial directions, the cooperating components including at least one spring on one of the spacer and the water rod.
摘要:
In a boiling water reactor having discrete bundles of fuel rods confined within channel enclosed fuel assemblies, an improved fuel design of bundles of fuel rods interior of the channels is disclosed. Specifically, partial length rods are utilized which extend from the bottom of the channel only part way to the top of the channel. These partial length rods are shortened with respect to the remaining rods and are symmetrically distributed throughout the fuel bundle with the preferred disposition being in the second row of the bundle of fuel rods from the channel wall. The symmetrical distribution of the partial length rods is at spaced apart locations one from another. The partial length rods extend from the bottom of the fuel bundle and terminate within the boiling region. during shutdown of the reactor, an improved cold shutdown margin is produced at the top of the fuel assembly due to the improved moderator-to-fuel ratio and reduction in plutonium formation at the upper portion of the bundle. Shutdown control rod worth is improved due to greater moderator-to-fuel ratio and a longer thermal neutron diffusion length. During power reator operation, the partial length fuel rods improve flow distribution above the ends of the partial length rods by channeling steam in the open interstitial area between rods above the ends of the partial length rods. This enables a high slip ratio of steam with respect to water and increases the density of the moderating water about the remaining rods in the upper region of the bundle at power operation. The total pressure drop is reduced, permitting more fuel rods in the design or a larger fuel rod diameter. The ratio of two-phase pressure drop to single phase pressure drop also is reduced, tending to increase the threshold for thermal hydraulic instability or coupled nucler-thermal-hydraulic instability. Rod spacers and bundle tie plates are provided with larger apertures overlying the partial length rods for further channeling of the steam and reduction of two-phase pressure drop. Most importantly and during full reactor power output, the pressure drop in the two-phase region of the bundle is reduced without substantial corresponding degradation of the fuel assemblies thermal limits. These features permit designs with larger fuel rod diameter than are possible without part length rods and results in a net increase in fuel assembly uranium weight with the larger fuel rod diameter more than compensating for the weight removed by shortening some of the fuel rods.