Abstract
To analyze the possibilities of using the system of partial neutron transport equations in evaluating the kinetics of a fast breeder reactors compared to the classical system of equations, computational studies of test models of MET-1000 and MOX-1000 reactors developed in the framework of the Generation-IV. As transient processes, the displacements (dumping and lifting) of control rods were simulated, and the reactivity effects in the indicated reactors were evaluated through the solution of stationary problems, i.e. through the use of an asymptotic estimate of the reactivity obtained from the solution of the stationary eigenvalue problem and from the processing of the inverse solution kinetic equation method from solving the transient problem. Test calculations were carried out in 26 and 28 group approximations using the BNAB-93 and BNAB-RF libraries and eight groups of delayed neutrons. The article shows that the features of determining, both calculation and measurement, the effects of reactivity and efficiency of control rods in fast breeder reactors are related to the working region of the neutron spectrum.
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