In Russia, it is planned to build a pilot demonstration fast lead-cooled reactor with an electric power of 300 MW (BREST-OD-300). Mixed nitride U-Pu fuel with minor actinides (MA) of energy composition will be used as nuclear fuel. Plutonium will be taken from the spent nuclear fuel (SNF) of a VVER-440. The isotopic composition of power plutonium can be different due to different storage periods and different burnup rates in spent nuclear fuel. It is practically unattainable to obtain a uniform isotopic composition.
The plutonium in the storage has a different content of the Pu239 isotope with a difference of more than 15%. This difference will affect the neutronic characteristics of the fuel in the reactor.
The paper considers the influence of fuel compositions with different composition of plutonium on the neutronic characteristics of the fuel and the equability of the BREST reactor operation.
In the BREST reactor, the equilibrium mode of the reactor operation requires a change in reactivity during fuel burnup within the effective fraction of delayed neutrons between refuelings, taking into account all processes accompanying the operation of the reactor.
|Speaker's email address||YEKarazhelevskaya@mephi.ru|
|Country/Int. organization||Russian Federation|
|Affiliation/Organization||National Research Nuclear University MEPhI|