METHOD FOR POWER MANOEUVRING A VVER OR PWR-TYPE NUCLEAR REACTOR

摘要

A method for power manoeuvring a VVER or PWR nuclear reactor is proposed which consists in using a traditional suite of means for influencing the reactivity of a reactor (control members of a control and safety system (CSS), boric acid, secondary loop pressure), in which the power (reactivity) is also regulated by adjusting the flow of coolant through the reactor. In a particular embodiment, the degree of heating of the coolant in a reactor is kept constant. The known and obvious effects of adjusting the flow rate in line with the power are that of minimizing or preventing temperature and pressure spikes in the primary and secondary loops and reducing the energy expended on the main circulation pump.