Induced nuclear reactions: processes – systems – and elements – With control of reactor – By movement of control element or by release of neutron...
Reexamination Certificate
1999-11-19
2001-08-14
Jordan, Charles T. (Department: 3641)
Induced nuclear reactions: processes, systems, and elements
With control of reactor
By movement of control element or by release of neutron...
C376S235000, C403S278000, C403S279000, C403S281000, C285S092000
Reexamination Certificate
active
06275556
ABSTRACT:
BACKGROUND OF THE INVENTION
This invention pertains to control rod drive mechanisms for a nuclear reactor and more particularly to an apparatus and method for preventing relative rotation of coaxial tubes forming a part of a control rod drive mechanism.
In a commercial nuclear reactor, heat, from which electricity is generated, is produced by fissioning of a fissile material such as enriched uranium. This fissile material, or nuclear fuel, is typically contained within a core made up of a plurality of fuel elements, coextensively arranged in a spaced parallel array. Movable control rods are dispersed throughout the core to control the fission process. The control rods generally comprise a plurality of elongated rods containing neutron absorbing materials, for example silver, indium and cadmium, which fit in openings among the fuel elements so as to be guided thereby during movement into and out of the core. Inserting a control rod into the core adds more absorber material and hence, decreases the nuclear reaction; conversely, withdrawing a control rod removes absorber material and hence, increases the nuclear reaction and thereby, the power output. The nuclear core and the control rods are positioned within and supported by a reactor vessel through which a reactor coolant flows.
Movement of the control rod into or out of the nuclear core is accomplished by control rod drive mechanisms that are mounted onto the top cover of the reactor vessel. One of the more commonly used types of control rod drive mechanisms is referred to as the “magnetic jack” type of mechanism. With this type of mechanism, the control rods are jacked into or out from the nuclear core in a series of motions each involving moving the control rod a discrete incremental distance. The jacking movement is accomplished by two sets of axially spaced magnet coils in conjunction with magnet plungers having gripper arms attached thereto by alternately and sequentially gripping, moving and releasing the control rod. One example of this type of control rod drive mechanism is shown and described in U.S. Pat. No. 5,009,834, entitled “Curvilinear Translating Latch And Linkage Arrangement In A Control Rod Drive Mechanism Of A Nuclear Reactor”.
Each of the previously mentioned movable control rods is engaged by a control rod drive shaft capable of moving the control rod slidably through an associated fuel rod grid. Each control rod drive shaft extends through an upper core plate and through an upper support plate that is spaced above the upper core plate, the upper support plate and the upper core plate being horizontally disposed in the reactor pressure vessel. The control rods that are engaged by the control rod drive shaft are slidably received in elongated thimble tubes disposed through the grid cells of each fuel assembly, which fuel assembly is in turn located below the upper core plate.
The control rod drive mechanisms are segmented for ease of assembly when positioning it within the reactor pressure vessel. However, during normal operation of the reactor, the liquid moderator coolant circulating in the reactor pressure vessel causes vibration of the internal components, including the control rod drive mechanisms, which are disposed in the vessel. Moreover, off-normal operation caused by seismic events and postulated accidents (e.g., loss-of-coolant accident) can also cause vibration of the internal components. It is desirable to prevent any possibility of unthreading of the threaded ends of the control rod drive mechanisms during normal and off-normal conditions because such unthreading, that may be caused by these vibrations, may lead to the elongated portions of the control rod drive mechanisms becoming disconnected at their threaded ends.
One well-known control rod drive mechanism uses threaded joints to connect cylindrical pieces. The stationary gripper plunger and the plunger half are two such cylindrical pieces that are threaded together. An anti-rotation screw radially penetrates both pieces to prevent the pieces from rotating relative to each other and becoming disengaged. Dynamic axial loads between the stationary gripper plunger and the plunger half were intended to be taken by the joint threads and not by the anti-rotation screw. However, part tolerances can combine to allow the dynamic axial loads to be taken by the anti-rotation screw. This can lead to failure of the anti-rotation screw.
Therefore, a problem in the art has been to provide means for preventing unthreading of the threaded ends of the control rod drive mechanism tubes when the control rod drive mechanism tubes are subjected to vibrations caused by normal operating conditions and when the control rod drive mechanism tubes are subjected to vibrations caused by off-normal operating conditions.
In addition to control rod drive mechanisms, reactor vessels also contain instrumentation tubes. U.S. Pat. No. 5,263,060 discloses a segmented instrumentation tube including a locking sleeve for interlocking the segments of the tube. That patent discloses an instrumentation tube having a first member having a threaded end portion that has a plurality of first holes spaced circumferentially around the outside surface thereof. The instrumentation tube also has a second member having an internally threaded end portion that has a plurality of second holes spaced circumferentially around the outside surface thereof. The internal threads of the second member are caused to threadably engage the external threads of the first member to produce a threaded joint therebetween. A sleeve having an inside surface surrounds the end portion of the first member and the end portion of the second member and thus surrounds the threaded joint. The sleeve includes a plurality of first projections and second projections that extend from the inside surface of the sleeve to engage the first holes and the second holes, respectively. The outside surface of the sleeve is then crimped or swaged at the locations of the first projections and second projections such that the first projections and the second projections engage their respective holes. In this manner, independent rotation of the first member with respect to the second member is prevented, so that the instrumentation tube will not unthread at its threaded joint when subjected to vibration.
By using a sleeve that has internal projections, the holes into which those projections extend, must be aligned with the projections. This establishes a predetermined fixed distance between the tubes and does not allow for axial adjustment of the tubes. In addition, the use of internal projections on the sleeve requires the sleeve to have a diameter large enough to permit the internal projections to slide over the outer surface of the tubes during initial assembly. Furthermore, tolerances in the dimensions of the projections can result in the circumferential load being carried by less that all of the projections.
There is a need for a device for locking a pair of threaded tubular members that provides for axial adjustment of the tubular members, does not require that the members assume a predetermined angular orientation with respect to each other, and distributes the circumferential load more evenly among the parts of a locking sleeve.
This invention provides a method and apparatus for preventing relative rotation of coaxial tube members of a control rod drive mechanism, suitable for use in a nuclear power reactor pressure vessel. The method and apparatus utilize a locking sleeve for interlocking the tube members, so that the threaded ends of the tube members do not unthread when subjected to vibration caused by normal and off-normal operation of the nuclear reactor.
A control rod drive mechanism constructed in accordance with this invention includes a first tubular member having a first threaded portion and a first generally cylindrical outer surface, the first tubular member including a first plurality of slots spaced circumferentially on the first outer surface and extending in a direction parallel to the axis of the first tubular m
Duga Martin E.
Guardiani Richard Frank
Kinney Calvin L.
Jordan Charles T.
Mun Kyongtaek K.
Westinghouse Electric Company LLC
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