Abstract: A control strategy for a pressurized water nuclear reactor that employs separate, independent control rod banks for respectively controlling Tavg and axial offset within corresponding deadbands. The strategy does not permit the control banks controlling reactor core power and the control banks controlling axial offset to move together, but normally gives preference to the control banks controlling the Tavg except when a demand signal is received simultaneously by both independent control rod banks to move in a same direction, in which case, the control bank compensating for the axial offset is given preference.

Abstract: A safe start-up of a boiling water reactor is achieved when two conditions are adhered to and monitored when the control rods are being moved out of the core: First, the drive of a control rod should be activated only when the directly and diagonally adjacent control rods remain at rest simultaneously, and, second, when all the directly adjacent control rods are still in the fully moved-in initial position.

Abstract: The operator of a nuclear steam supply system manually selects a lineup of either one, two, or three main feedwater pumps for normal reactor operation to generate power. This selection sets or resets a status latch for each pump, representative of intended pump operation.

Abstract: A reactor protection system having four divisions, with quad redundant sensors for each scram parameter providing input to four independent microprocessor-based electronic chassis. Each electronic chassis acquires the scram parameter data from its own sensor, digitizes the information, and then transmits the sensor reading to the other three electronic chassis via optical fibers. To increase system availability and reduce false scrams, the reactor protection system employs two levels of voting on a need for reactor scram. The electronic chassis perform software divisional data processing, vote 2/3 with spare based upon information from all four sensors, and send the divisional scram signals to the hardware logic panel, which performs a 2/4 division vote on whether or not to initiate a reactor scram. Each chassis makes a divisional scram decision based on data from all sensors. Each division performs independently of the others (asynchronous operation).

Abstract: A control rod cluster assembly of a nuclear reactor is repeatedly repositioned in a guide tube assembly above a fuel assembly in the reactor core in single steps at separate times during a single fuel cycle. For instance, the single-step repositioning can be repeated once every month or every four months in a twelve month fuel cycle.

Abstract: A high temperature pebble bed nuclear reactor having a medium power capacity of 300 to 500 MW.sup.e is equipped with two different shut-down arrangements comprising reflector rods used exclusively for scram. The total shut-down reactivity of the reflector rods is proportioned in order to prevent the excessive cooling of the reactor core folowing scram. In this manner, the reactor core is rendered subcritical (in the event of accidents, for example, or at the beginning of any operating state) yet capable of returning to criticality at a reduced level of temperature and power output following the removal of heat. The use of all of the reflector rods for scram is effected only in the event of reactivity accidents. For all other scram incidents, only a portion of the reflector rods are used.

Abstract: In a pressurized water reactor in which a dropped control rod is detected by a negative rate of change of neutron flux which exceeds a preset negative limit, the reactor is only shutdown if the axial offset exceeds a preselected limit, so that it is possible to maintain power, and in many cases full power, despite the presence of a dropped rod. Where part length control rods are used during power changes, separate limiting values on axial offset are used when these rods are fully inserted and when they are fully retracted.

Abstract: In the operation of a boiling water reactor, when the core flow rate is decreased due to a trip of the circulating pump, the control rod pattern is suitably changed to avoid unnecessary scram of the control rods. The change of the control rod pattern is made by driving control rods which have been inserted to small depth deeper into a depth near 12/24 of the core height. In addition to this control rod operation, the control rods which have been inserted to large depth are withdrawn to a depth near 12/24 or, alternatively, the control rods which have not been inserted at all are inserted to the depth of about 12/24 of the core height.

Abstract: When the control parameter (.DELTA.T) is within its deadband, a correction of the axial deviation of power (DA) is effected by movement of at least one group of control rods, when DA is outside a predetermined range or deadband straddling a reference value DA ref. The group which is moved is chosen as a function of the sign of .DELTA.T, of the position of .DELTA.T with respect to its deadband and of the position of the other groups. When .DELTA.T is outside its deadband, the differences between the amplitudes of insertion of the groups participating in the control of the reactor are made to vary by stopping or starting of groups selected as a function of the positions of the groups of rods (G1, G2, N1, N2) in the core of the reactor and of the position of DA either with respect to its deadband if DA is outside this deadband, or with respect to DA ref, if DA is within this deadband.The invention is in particular applicable to pressurized-water nuclear reactors.

Abstract: Nuclear reactor core safety rod release apparatus comprises a control rod having a detent notch in the form of an annular peripheral recess at its upper end, a control rod support tube for raising and lowering the control rod under normal conditions, latches pivotally mounted on the control support tube with free ends thereof normally disposed in the recess in the control rod, and cam means for pivoting the latches out of the recess in the control rod when a scram condition occurs. One embodiment of the invention comprises an additional magnetically-operated latch for releasing the control rod under two different conditions, one involving seismic shock.

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.