Safety system esp. for pressurised water reactor - images each primary circuit loop by computer and initiates localised remedial action for a fault

摘要

A method of ensuring correct cooling and safety of a nuclear reactor, esp. pressurised water reactor in which there are several primary coolant loops connected to the pressure vessel consists of measuring the pressure and flow rates in the loops and evaluating these to detect faults. For each loop the coolant flow rate is imaged by a computer; temporary pronounced deviations from this image are then compared with the image and used for triggering actuators to influence the coolant flow. Pref. the imaging of the coolant flow itself takes account of the position of the actuators. Where a number of loops are connected to a single header or distributor, a faulty loop is sepd. from the header. The control signal may then also bring into use a redundant loop. Without excessive expenditure on measuring equipment it is possible to detect and localise deviations from normal coolant operation with such accuracy that much more detailed and localised remedial measures can be set in motion than hitherto.