Patent Number: 052415708
Section: description

DESCRIPTION OF THE PREFERRED EMBODIMENTS In accordance with the present invention, a boiling-water reactor 10 comprises a vessel 12, a dryer 14, a steam separator 16, a chimney 18, a core 20, and core-control assemblies 22(A-D), as shown in FIG. 1. Vessel 12 includes a top head 24, a bottom head 26 and a sidewall 28. Core 20 includes fuel bundles, including fuel bundles 31-36. Each fuel bundle contains fuel rods of fissile fuel. Chain reactions of this fissile fuel provide a sustained power output from reactor 10. In normal operation, water flows into core 20 from below. Most of the water rising through core 20, as indicated by arrow 40, is converted to steam. Chimney 18 supports a steam head, promoting natural circulation of water within vessel 12. Steam separator 16 removes most of the water from the steam/water mixture rising from chimney 18. The separated water is directed radially from steam separator 16 and down a downcomer 42, as indicated by arrow 44. Water exiting downcomer 42 flows into a lower plenum 46, wherein core-control assemblies 22 are located. Water in lower plenum 46 is recirculated up through core 20 as indicated by arrow 48. Dryer 14 removes any remaining water in steam rising from steam separator 16. The steam then exits vessel 12 via a main steam line nozzle 50. The exiting steam drives a turbine (not shown) which drives a generator (not shown) to produce electricity. As it drives the turbine, the steam condenses; the resulting condensate can be returned to vessel 12 via a feedwater return nozzle 52. Each core-control assembly 22A-D includes a respective control rod 60A-D, a respective fuel support 62A-D, a respective control-rod guide tube (CRGT) 64A-D, a respective control-rod drive 66A-D, and a respective control-rod-drive (CRD) housing 68A-D. CRD housings 68 extend through and are welded to stub tubes 70, which are in turn welded in apertures through bottom head 26. CRD housings 68 serve to support control-rod drives 66 and respective CRGTs 64. CRGTs 64 in turn support respective fuel supports 62, to which they are welded. Each fuel support 62 can contact and support four fuel bundles. For example, fuel support 62A contacts and supports fuel bundles 31 and 32 plus two others that are hidden by other components in FIG. 1. Fuel bundles 31-36 are held vertical by a top guide 72, which is basically a grid with openings above each respective fuel bundle. A core plate 74 similarly provides lateral stability for CRGTs 64 and fuel supports 62. Control-rod drives 66 support and provide for vertical motion of respective control rods 60. Each control rod 60A-D has a respective coupling socket 76A-D. Each coupling socket 76A-D provides for bayonet engagement with a respective control-rod drive 66A-D. Core-control assemblies 22 regulate the power output from core 20. Control-rod drives 66 control the vertical positions of respective control rods 60. Control rod 60A is in a fully retracted position that provides for maximum power output. Control rod 60B is in an intermediate position providing for intermediate power. Control rod 60C is in a minimum power position. Control rods 60 have a cruciform cross section capable of controlling the neutrons to the four fuel bundles supported by the respective fuel support 62. In its minimum power position, control rod 60C absorbs a maximum number of neutrons that would otherwise travel between fuel bundles, e.g., between fuel bundles 35 and 36. When all control rods are so inserted to their minimum power positions, core 20 becomes subcritical and reactor 10 can be shut down. Control rod 60A is fully retracted to a maximum power position. It does not absorb a significant number of neutrons passing between fuel bundles. Thus, with control rod 60A in this maximum power position, fuel bundles 31 and 32 provide their maximum power outputs. Control rod 60B is in one of a continuum of intermediate power positions so that fuel bundles 33 and 34 provide an intermediate level of power. Control rod 60C is shown in a minimum power position. In the preferred embodiment, this minimum power position is also the decoupling position at which control rod 60C can be rotated and decoupled. As long as adjacent fuel bundles are in place, a control rod cannot be rotated, and thus cannot be decoupled. However, once the adjacent fuel bundles are removed, the control rod can be rotated and decoupled. In an alternative embodiment, a control rod is not decoupled at the minimum power position. Instead, overtravel beyond the minimum power position is required. This overtravel is only achievable after respective fuel bundles are removed from the respective fuel support. For conciseness of illustration, control rod 60D is shown in the overtravel position used for decoupling in the alternative embodiment in FIG. 1. With fuel support 62D cleared and control rod 60D in the decoupling position, control rod 60D can be rotated to permit decoupling of the bayonet engagement of coupling socket 76D from control-rod drive 66D. Control rod 60D can then be removed from vessel 12. The present invention provides for the removal of a control rod in accordance with a method 200 illustrated in FIG. 2. In step 201, all control rods are inserted to their minimum power positions (in which control rod 60C is shown) and the reactor is shut down. In step 202, top head 24, dryer 14, and steam separator 16 are removed to provide access to core 20. The four fuel bundles associated with the control rod are removed at step 203. Where overtravel is required, this is performed at step 204 (shown in a dashed box to indicate that this step is conditional on the embodiment). At step 205, the control rod is rotated to decouple the bayonet connection. At step 206, the control rod is lifted out of reactor vessel 12. One of the control rods 60 is shown in greater detail in FIG. 3. Control rod 60 has four blades 302, providing its cruciform cross section. Each blade 302 is filled with neutron-absorber rods 304 held in place by a sheath 306. Each blade 302 has a series of holes 308 that provide for coolant flow in and out of control rod 60. At the top of control rod 60 is a handle 310 providing for convenient insertion and removal of control rod 60 from above. Near handle 310 are four fins 312 that provide lateral support when they engage top guide 72 at the minimum and the decoupling position. Blades 302 are notched above coupling socket 76 to provide clearance relative to the respective fuel support 62. Four coupling rollers 314 on coupling 76 reduce friction and guide vertical movement of control rod 60 within CRGT 64. Blade rollers 316 provide spacing and reduce friction between control rod blades 302 and adjacent fuel bundles, as is known in the art. Smooth metal pads can be used in place of rollers for the same purposes. Fuel support 62 and CRGT 64 are shown in FIG. 4. Fuel support 62 has a cruciform aperture 402 through which control rod 60, shown in FIG. 5, extends and moves. Rounded apexes 404 of cruciform aperture 402 engage coupling socket 76 when it is at the proper level. Fuel support 62 has four depressions 406 that cradle and support fuel bundles. Fuel support 62 also has four bottom ports 408 through which water enters core 20. CRGT 64 is cruciform in shape to provide lateral support to the lower end of control rod 60. CRGT 64 has an elongated body 412 that is long enough to substantially contain control rod 60 when the latter is in its fully retracted position. At its base, CRGT 64 has a bayonet coupling 414 with four tabs 416. Bayonet coupling 414 provides for locking engagement of CRGT 64 with a respective control rod drive 66. The bayonet connections of control rod 60 to control-rod drive 66 in a core-control assembly 22 are shown in FIG. 6, in which control rod 60 is fully inserted. Control-rod drive 66 includes a hollow piston 602 that moves vertically with control rod 60. Hollow piston 602 has four fingers 604 at its top, as shown in FIG. 6. A cylindrical spacer 606 provides radial support for these fingers 604. Coupling socket 76 of control rod 60 has a slotted opening 608 at its base for admitting fingers 604 when control rod 60 is lowered with an orientation 45.degree. from that it assumes during reactor operation. A 45.degree. clockwise rotation of control rod 60 secures the coupling. Fuel bundles can then be placed on fuel support 62. To decouple, fuel bundles are removed and a 45.degree. counterclockwise rotation aligns fingers 604 with slotted openings 608 to permit decoupling. While the foregoing has described its preferred embodiments, the present invention provides for considerable variation. As indicated above, some embodiments involve overtravel to reach a decoupling position, while others do not. Different control rods are provided for; for example, a control rod can include neutron-absorbing plates instead of rods. While the illustrated embodiment utilizes notched control rod, a beveled control rod and a control rod with a conventional squared bottom are also provided for. The present invention is not limited to control rods with cross sections in the shape of four pointed stars. For example, cross sections with three or six points are provided for, for example where hexagonal or triangular fuel bundles are used. The same options are provided for the fuel support aperture. The nature of the cross section affects the degree of rotation required for coupling and decoupling. These and other modifications to and variations upon the described embodiments are provided for by the present invention, the scope of which is limited only by the following claims.