Patent Number: 048428051
Section: claims

1. A method of detecting the fall of an anti-reactive element into the reactor of a nuclear power station, said method being characterized by the fact that variations are monitored firstly in the nuclear power of the reactor under the control of a loop for regulating said power and secondly of at least one external parameter related to events outside the reactor and used in calculating the power reference value which is supplied to said regulation loop in order to control the reactor, said fall being detected by the fact that a rapid drop in said power is detected while no large external parameter variation is detected with a predetermined time relationship to said rapid drop. 2. A nuclear power station having a reactor protected against the fall of an anti-reactive element, said reactor comprising: a core containing fissile fuel elements for maintaining a nuclear reaction providing nuclear power;  a cooling fluid circuit having a branch passing through said core to remove said power in the form of heat and to enable said heat to be utilized outside the reactor;  measurement means for continuously measuring the current nuclear power of the reactor;  anti-reactive regulation elements suitable for reversibly reducing said power; and  regulation drive means controlled by said power measurement means in order to cause said regulation elements to penetrate to a greater or lesser extent into said core depending on whether the current nuclear power is greater than or less than a power reference value, in such a manner as to constitute a nuclear power regulation loop and to enable the reactor to be controlled by varying said reference value, with any reaction of said loop giving rise to transient power variations before settling if possible;  at least one anti-reactive element being suspended above a passage into said core such that an accidental fall of said element causes it to penetrate into the core, thereby initiating a rapid decrease in nuclear power, followed by a reaction from said regulation loop, which reaction is accompanied by transient variations in said power prior to said power settling back on its value prior to said fall;  said reactor further including stop means under the control of a reactor stop signal; and  accident detection means for providing such a reactor stop signal after an accident in the core, in particular such a fall of an anti-reactive element, and thus for protecting the reactor against the damage which would result if said reaction were to continue without the accident being repaired;  said power station further including:  a power outlet member receiving inlet thermal power from another branch of said cooling fluid circuit and providing variable and/or interruptible outlet power to a load; and  at least one nuclear power regulating system receiving the values of parameters external to the reactor such as parameters relating to the operation of said power outlet member, and generating said power reference value in response thereto in order to continuously match the current nuclear power to variations in said parameters so that if such a variation is large it is capable of causing a rapid variation in nuclear power;  said power station being characterized by the fact that said accident detection means comprise a circuit specifically for detecting the fall of an anti-reactive element, said circuit being suitable for detecting firstly rapid drops in nuclear power and secondly said large variations in at least one said external parameter, and for providing a said reactor stop signal (15) when such a drop in nuclear power is detected with no such external parameter variation in a predetermined time relationship with said drop.  a nuclear power monitoring circuit comprising differentiating means (4c) receiving a measurement signal representative of said power (3) and delivering a derivative signal (11) which is differentiated with respect to time; and  threshold means (6j) receiving said derivative signal and delivering a signal (12j) representative of a rapid drop in nuclear power when said power drops at a rate greater than a predetermined rate;  at least one external parameter monitoring circuit, each such circuit including differentiator means (4a, 4b) receiving a measurement signal (1, 2) representative of such a parameter and delivering a derivative signal (9, 10); and  threshold means (6e, 6f, 6g, 6h) receiving the, or each, said derivative signal and providing a signal (12e, 12f, 12g, 12h) representative of large variation in an external parameter when any such derivative signal leaves a predetermined range; and  a logic circuit (13, 14) having its inputs connected to said monitoring circuits in order to provide said reactor stop signal (15) on receiving a signal representative of a rapid drop in nuclear power (optionally after a delay) without receiving a signal representative of a large variation in an external parameter (optionally after a delay).  said logic circuit (13, 14) comprising means (13) for logically adding the output signals from said monitoring circuits.  said logic circuit (13, 14) providing said reactor stop signal (15) when said signal representative of a rapid drop in the current nuclear power (12j) is present and none of said delayed and non-delayed signals representative of a large variation in an external parameter is simultaneously present.  said cooling fluid circuit includes cooling loops each of which comprises a primary pressurized water circuit and a secondary water and steam circuit, the primary circuit cooling said core, the secondary circuit including at condenser and a steam generator heated by said primary circuit, each of said circuits including a pump for circulating water;  said means for measuring nuclear power are chambers sensitive to return flux and disposed in said core;  said anti-reactive regulation elements are control clusters each comprising a plurality of vertically-suspended rods that penetrate to a greater or lesser extent into passages in said core, each of said cluster simultaneously constituting one of said anti-reactive elements capable of suffering an accidental fall;  said power outlet member comprising at least one steam turbine driven by the steam from at least one of said secondary cooling fluid circuits and driving an alternator;  said load being an electricity supply grid fed from said alternator;  control means being provided on said cooling fluid secondary circuit to control the steam pressure at the inlet to the turbine as a function of the turbine speed and/or the electrical conditions at the alternator outlet, in such a manner as to constitute a regulation loop for the turbine-alternator assembly; and  circuit breaking means are provided to isolate the alternator from the grid in the event of a grid fault or when necessary for power station operation.  said power station being characterized by the fact that said circuit for detecting a fall includes two of said circuits for monitoring large variations in external parameter, one of said circuits (4b, 6g, 6h) detecting variations in steam pressure at the inlet to the turbine, and the other (4a, 6e, 6f) detecting variations in the speed of the pump in said primary circuit. 3. A power station according to claim 2, characterized by the fact that said circuit for detecting a fall comprises: 4. A power station according to claim 3, characterized by the fact that said circuit for detecting a fall comprises a plurality of said circuits for monitoring external parameters (4a, 4b, 6e, 6f, 6g, 6h) each detecting variations in a corresponding external parameter. 5. A power station according to claim 3 characterized by the fact that said circuit for detecting a fall comprises at least one delay means (5a, 5b) for delaying the measurement signal or a signal (9, 10) derived from the measurement signal (1, 2) of at least one of said external parameters in order to provide at least one signal (12a, 12b, 12c, 12d) representative of a large variation in an external parameter which signal is delayed relative to another non-delayed signal (12e, 12f12g, 12h) representative of a large variation in the same parameter; 6. A power station according to claim 4, wherein: 7. A power station according to claim 6, wherein said pump for the primary cooling fluid circuit is driven by a motor fed with electricity from said alternator such that the speed of said pump varies with the speed of said alternator and said turbine;