Abstract:
In a nuclear reactor power control system, when a control rod or a safety rod drops into a nuclear reactor by a failure of a control rod drive mechanism, a power of a summing and averaging circuit which sums and averages measurements of neutron detectors is smaller than a value A preset by an operator of the nuclear reactor. The averaged value of the neutron detector outputs is compared with the preset value A, and if the difference therebetween exceeds a preset limit signal level B for the output drop, automatic withdrawal of the control rod is stopped, and if the difference is smaller than the limit signal level B for the power drop, the control rod is withdrawn by the amount corresponding to the power drop.
Abstract:
An apparatus is disclosed which measures forces resisting the movement of pistons in a control rod drive mechanism in a nuclear reactor and which includes pressure sensing means and further includes hydraulic circuitry to divert pressurized fluid from a normal operating conduit to a selected shunt conduit containing a valve having a particular fluid control characteristic, said shunt conduit directing the fluid to a selected piston to move said piston and said pressure sensing means measuring the pressure of the fluid during the motion of said piston to give an indication of the force needed to achieve such motion.
Abstract:
A power control apparatus of a boiling water atomic reactor for transferring the atomic reactor to a low power stand-by operation when a load of a generator is rejected. The necessity of insertion of control rods into a core is decided in accordance with the state of the atomic reactor when a load rejection occurs. When the insertion of control rods is required selected control rods are inserted into the core and a core flow rate is reduced to transfer the atomic reactor to the low power stand-by operation. When the insertion of control rods is not necessary only the reduction of core flow rate is performed.
Abstract:
Nuclear reactor safety rod release apparatus comprises a ring which carries detents normally positioned in an annular recess in outer side of the rod, the ring being held against the lower end of a drive shaft by magnetic force exerted by a solenoid carried by the drive shaft. When the solenoid is de-energized, the detent-carrying ring drops until the detents contact a cam surface associated with the lower end of the drive shaft, at which point the detents are cammed out of the recess in the safety rod to release the rod from the drive shaft. In preferred embodiments of the invention, an additional latch is provided to release a lower portion of a safety rod under conditions that may interfere with movement of the entire rod.
Abstract:
A method of operating a nuclear reactor adapted to use cross-shaped control rods. The control rods are grouped into a plurality of groups having a first group consisting of a control rod located at the center of the core, a second group consisting of 8 control rods surrounding the control rod of the first group, a third group consisting of control rods located adjacent to and outside of the control rods of the second group, and other groups determined successively in the same manner as in the third group. During the operation period other than the period in which the number of the control rods to be inserted for realizing the critical condition of said nuclear reactor is less than 6, the nuclear reactor is operated with control rod patterns in which the inserted control rods are selected from control rods of alternate or every other groups of said groups so as to include at least a pair of control rods which are located in a similar manner to that of the KNIGHT's movement on a chess board.
Abstract:
Improvements in high temperature gas cooled nuclear reactors is effected by an arrangement of paired absorber elements, each pair comprising a rod shaped absorber element and a tubular absorber element generally surrounding the rod shaped element. With this paired combination in a reactor employing spherical fuel elements, the effective life of the absorber rods is significantly extended by protection of the rod shaped absorber element from excessive amounts of irradiation from thermal neutrons.
Abstract:
A retainer to provide supplemental holddown force for a control component assembly latched into a fuel assembly of a nuclear reactor. Upon failure of latching mechanism the retainer precludes the ejection of the control component assembly from the fuel assembly by the upward coolant flow drage force. The spring loaded retainer is mounted at the top of the control component assembly and engages both the control component assembly and the core grid plate to form a structural blocking of the grid plate hole thereby precluding the ejection of the control component assembly therethrough.
Abstract:
A control rod drive attaching and detaching device and a control rod drive handling device are mounted on a revolving device to be movable independently from each other. The control rod drive attaching and detaching device includes bolt handling means for loosening and tightening bolts for fastening a control rod drive to a pressure vessel of a nuclear reactor, coolant splash preventing means for disposing of coolant which flows from the control rod drive when the latter is detached from the pressure vessel, and uncoupling means for uncoupling a control rod from the control rod drive. The control rod drive handling device includes a column pivotally mounted on a carriage, a cart removably mounted on the column, and means for moving the column to a horizontal position. Each control rod drive mounted to the pressure vessel of the nuclear reactor is detached from the pressure vessel by the control rod attaching and detaching device and transferred to the cart of the control rod drive handling device. The column is moved to a horizontal position, and the cart with the control rod drive supported thereon is removed from the column.
Abstract:
Earthquake-proof mounting support for control rod drives of nuclear reactors having a generally cylindrical reactor pressure vessel formed with a convex wall at least at one end thereof and including control rods with control rod drive shafts coupled thereto and mounted so as to be movable in axial direction thereof within tubular drive housings extending pressure-tightly through the end convex wall and sealed against the outside, the tubular drive housings comprising tube member forming respective feed-through passageways for the control rod drive shafts, the tube members having respective portions thereof extending with respectively varying lengths outside and beyond the convex wall to a given horizontal plane, and a support grid formed of a plurality of grid bars articulatingly connecting the tube members at respective free ends thereof outside the convex wall, respectively, to one another.
Abstract:
A method and apparatus for removing, in an essentially continuous operation, the control rods and the upper guide structure from a nuclear reactor vessel during refueling. The apparatus includes a rigid frame which is secured to the upper guide structure after the vessel head is removed. A platform is vertically reciprocable within the frame and is adapted to engage and lift simultaneously all control rod drive shafts to a maximum elevation within the frame. A mechanical interface between the platform and the frame is provided so that continuation of the lifting force on the platform transfers the lift force to the frame whereby the upper guide structure is lifted out of the vessel. Automatically operated stop means are provided to lock the platform and rods in the maximum elevation within the frame in order to prevent accidental dropping of the rods during transfer of the upper guide structure and control rods to a temporary storage area.