Consider, now, that a large, sudden reactivity is inserted into the reactor
while working at nominal power. In this case the time to be considered between
neutron generations is the prompt time, i.e., for a PWR,
=0.1 ms.
The power increase is too fast for the cooling system to be efficient any
more. The cooling system is no more efficient and melt down of the fuel
elements may occur. Boiling of the water coolant leads to a strong decrease of
the reactivity and to a limitation of the power surge. In other types of
reactors like RMBK and fast reactors the decrease of the reactivity only
occurs due to the fuel dissemination.
In conclusion we see that the safety of critical neutron reactors depend strongly on the delayed neutrons fraction of the fuel as well as on the temperature coefficients, especially on the Doppler temperature coefficient. These strong dependences severely constrain the type of fuel which can be used in critical reactors in safe enough conditions. We shall see that hybrid reactors might be very helpful in alleviating these constraints.