Framatome & Cie.

Pierre Ruiz

Jean L Leroy

A device and method for determining the power of a pressurized water nuclear reactor, comprising measurement of the neutron power (15) and of the temperature of the primary fluid in the cold branch (1) and in the hot branch (1'), computing (2, 4, 6, 8, 12) the thermal power of the reactor from these temperature measurements (1, 1'), comparing (14) the thermal power signal (13) and the neutron power signal (16) and correcting (22) the neutron power signal (16). The device in addition comprises means for fast and precise determination of the secondary power of the reactor by comparison of a first signal of the secondary thermal power (13) established by means of the temperature measurements (1, 1') and a second signal of the thermal power (16') established by means of a simplified secondary heat balance (25).

Device for determination of the power of a pressurized water nuclear

Process and device for the detecting of faults in the distribution of the power of the core (2) of a pressurized water nuclear reactor, in which at least one parameter representing the power of the core (2) is measured, each parameter being measured at a determined number of points. For each parameter, the difference between the two extreme measured values and the ratio of this difference to the smallest measured value are determined, and this ratio is compared to a set value, a fault being detected if this ratio is greater than the set value. The sensors (4, 9) are arranged symmetrically close to the periphery of the core (2) and a further sensor (9) is placed close to the center of the core (2).

Process for detecting faults in the power distribution of a pressurized

Process and device for the detection of the variations, due to a fault in the position of the core control clusters, in the reactivity of the core of a reactor. A momentary value (6) representing the reactivity calculated directly from the core neutron power (2) is compared to a momentary value (30) representing the reactivity calculated from the momentary mean temperature (25) in the core and the mean boron concentration (29) in the primary fluid passing through the core. The invention applies to pressurized water nuclear reactors.

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Blanc Mesnil, France

Pierre Ruiz