Patent Number: 051587386
Section: claims

1. Method of controlling a pressurized water nuclear reactor comprising a nuclear reactor and plurality of control bars adapted to be selectively and individually positioned in the reactor core for controlling the reactivity of the core, the negative reactivity provided by said control bars when fully inserted in the core being sufficient for compensating all reactivity variations which may intervene during normal operation of the reactor and upon an incident which requires that the reactor be rendered sub-critical while the pressurized water is at the normal temperature for operation of the reactor, said method comprising the steps of: (a) determining: the current value of an operating parameter indicative of the power developped by the reactor core; the current positions of the control bars; and the axial power distribution offset in the core;  (b) when the difference between said current value of the operating parameter and a set value exceeds a predetermined deadband interval, computing the amount by which the reactivity of the core should be modified;  (c) determining, through a simulation process on a model of said reactor, which ones of the control bars may be moved and predicted amounts of displacement to be given to said ones of the bars for bringing back said difference within said deadband without modifying said axial power distribution offset out of a reference range and while minimizing a core enthalpy increase factor; and  (d) moving said ones of said bars by said amounts of movement.  comprising the steps of:  (a) measuring the current value of an operating parameter indicative of the power developped by the reactor core, the current positions of the control bars and the axial power distribution offset in the core,  (b) when the difference between said current value of the operating parameter and a set value exceeds a predetermined deadband interval, computing the amount by which the reactivity of the core should be modified and the change in the negative reactivity provided by said control bars which is necessary for decreasing said difference to zero,  (c) randomly selecting at least one bar within the core or within a sector of the core and simulating changes in negative reactivity to be expected from a plurality of assumed amounts of movement of said at least one bar, said assumed amounts of movement having an average value substantially equal to the amount of movement which would result in the necessary negative reactivity change,  (d) computing the predicted variation of the axial power distribution offset which would result from each of said assumed movements and determining whether said predicted variation results in an axial power distribution offset exceeding a predetermined reference value,  (e) if said predetermined reference value is exceeded, repeating steps (c) and (d) until the variation of axial power distribution offset does not result in a power axial offset exceeding said predetermined reference value,  (f) computing the variation of an enthalpy elevation factor of the core resulting from the simulated amount of movement,  (g) storing the simulated amount of movement of said at least one bar if said simulated amount of movement decreases the enthalpy factor, while storing or omitting to store said simulated amount of movement with a probability which is responsive to the degree of said variation if said simulated amount of movement increases the enthalpy factor,  (h) repeating steps (b)-(g) until the accumulated negative reactivity change due to the stored amount of movement is equal to the necessary change, with a permissible deviation, and  (i) moving said at least one bar by said stored amounts of movement.  kT is a constant value which is greater than the maximum value of .DELTA. (F.DELTA.H) by at least one order of magnitude.  comprising the steps of:  (a) determining: the current value of an operating parameter indicative of the power developped by the reactor core; the current positions of the control clusters; and the axial power distribution offset in the core;  (b) when the difference between said current value of the operating parameter and a set value exceeds a predetermined deadband interval computing the amount by which the reactivity of the core should be modified;  (c) determining, through a simulation process on a model of said reactor, which ones of the control clusters may be moved and predicted amounts of displacement to be given to said ones of the bars for bringing back said difference within said deadband while minimizing a core enthalpy increase factor;  (d) after determining each said predicted amount of displacement computing the resulting axial offset, verifying that the predicted amount of displacement does not cause the axial offset difference to move out of a predetermined reference range, discarding the predicted displacement if it exceeds in the affirmative and retaining the predicted amount of displacement in the negative; and  (e) moving said ones of said clusters by said amounts of movement. 2. Method of controlling a pressurized water nuclear reactor comprising a nuclear reactor and a plurality of control bars adapted to be selectively and individually positioned in the reactor core for controlling the reactivity of the core, 3. Method according to claim 2, wherein the variation in the axial power distribution offset is computed after said at least one bar and the amount of displacement to be given to said at least one bar have been stored. 4. Method according to claim 2, wherein said probability is computed as: EQU P=exp[.DELTA.(F.DELTA.H)/kT] 5. Method according to claim 4, wherein kT is initially given a value which leads to a probability which is close to 1 and is progressively decreased as long as the probability retains an average value which is higher than a predetermined value. 6. Method according to claim 2, further comprising fractionating said core into a plurality of virtual angular sectors all having the same arrangement, wherein all control bars having the same positions in all sectors are simultaneously moved by the same extent. 7. Method according to claim 6, wherein said bars having the same positions in the different angular sectors are moved by the same extent. 8. Method according to claim 6, wherein said bars having the same positions in the different angular sectors are moved by different extents and the different extents are selected by applying a correction about an average value which compensates for radial power offsets. 9. Method according to claim 2, wherein the reactor is maintained in sub-critical condition after it has been shut-down with additional bars each having a neutron absorption which is approximately double that of a control bar. 10. Method according to claim 2, comprising the additional step of modifying the neutron energy spectrum by progressively removing bars which contain burnable poison from the core. 11. Method according to claim 2, wherein said control bars are distributed in pairs, the two bars of a same pair being at a same location in the core. 12. Method of controlling a pressurized water nuclear reactor comprising a nuclear reactor and a plurality of control clusters adapted to be selectively and individually positioned in the reactor core for controlling the reactivity of the core, the negative reactivity provided by said control clusters when fully inserted in the core being sufficient for compensating all reactivity variations which may intervene in normal operation of the reactor and upon an incident which requires that the reactor be rendered sub-critical while the pressurized water is at the normal temperature for operation of the reactor,