摘要:
A method and apparatus for increasing the reliability of linear drive devices of a nuclear reactor to scram the control elements held in a raised position thereby. Each of the plurality of linear drive devices includes a first type of holding means associated with the drive means of the linear drive device and a second type of holding means distinct and operatively dissimilar from the first type. The system of linear drive devices having both types of holding means are operated in such a manner that the control elements of a portion of the linear drive devices are only held in a raised position by the first holding means and the control elements of the remaining portion of linear drive devices are held in a raised position by only the second type of holding means. Since the two types of holding means are distinct from one another and are operatively dissimilar, the probability of failure of both systems to scram as a result of common mode failure will be minimized. Means may be provided to positively detect disengagement of the first type of holding means and engagement of the second type of holding means for those linear drive devices being operative to hold the control elements in a raised position with the second type of holding means.
摘要:
In a light water reactor system using the thorium-232 -- uranium-233 fuel system in a seed-blanket modular core configuration having the modules arranged in a symmetrical array surrounded by a reflector blanket region, the seed regions are disposed for a longitudinal movement between the fixed or stationary blanket region which surrounds each seed region. Control of the reactor is obtained by moving the inner seed region thus changing the geometry of the reactor, and thereby changing the leakage of neutrons from the relatively small seed region into the blanket region.The mechanical design of the Light Water Breeder Reactor (LWBR) core includes means for axially positioning of movable fuel assemblies to achieve the neutron economy required of a breeder reactor, a structure necessary to adequately support the fuel modules without imposing penalties on the breeding capability, a structure necessary to support fuel rods in a closely packed array and a structure necessary to direct and control the flow of coolant to regions in the core in accordance with the heat transfer requirements.
摘要:
A device for handling fuel, breeder or absorber rods of nuclear reactors, particularly liquid-metal cooled nuclear reactors, with a hoisting unit situated on a slotted rotary cover and with a remote control grip for grasping the rods, and means for moving the hoisting unit along the slot. Thus, rotation of the cover and movement of the hoisting unit along the slot permits the grip to be moved into position for transfer of any desired rod-shaped member. The slot in the reactor rotary cover as well as the handling device are enclosed by a shielding box.
摘要:
Vertical control rod includes an absorber formed of flexible members and suspended by a traction device below the reactor core during operation of the reactor and a tensional spring for drawing the absorber into the reactor core to shut off the reactor. The control rod is operable independently of gravity and avoids jamming of the absorber in the guide therefor.
摘要:
A control rod drive mechanism for a nuclear reactor including means for preventing the excessive compressive loading of the control rod by the control rod drive motor. The drive motor is constructed with a ''''floating'''' rotor assembly for allowing it to translate upwardly in response to a compressive overload. The rotor is defined as comprising two pivoted segments with one of the rotor segments adapted for engaging a stop provided for the pressure housing of the control rod drive mechanism. When a compressive overload occurs, the rotor translates until the housing stop and rotor interengage so that the rotor torque is transferred from the control rod to the pressure housing. A compressive overload condition exists whenever the friction loading exceeds the combined weight of the control rod and associated components.
摘要:
A control rod drive mechanism for positioning a control rod in a nuclear reactor. The control rod having a part length poison portion for positioning in the reactor core. The mechanism coacting with a pressure housing and including an energizable stator mounted on the outside of the pressure housing and a rotor responsive to the stator mounted on the inside of the pressure housing for positioning a control rod. A rotor tube is movably mounted with a translating leadscrew and positioned within the rotor to be rotatably responsive to the magnetic field coupled thereto from the stator. The part length control rod is connected to the leadscrew and movable therewith. The rotor carries a nut assembly for engagement with the leadscrew to cause the leadscrew to be responsive to the rotations of the rotor and thereby the positioning of the control rod. The rotor is constructed of two pivoted segments adapted to pivot in opposite directions in response to the energization and deenergization of the stator for providing an unlocking and locking action of the rotor by moving one of the segments against the pressure housing to effect the braking action of the rotor and effective for preventing translation of the leadscrew.