The spatial kinetics of the nuclear reactor has been so far studied by means of the modal expansion method. The transfer functional expressions of the modal response have also been made use of.
It is, however, rather difficult to do the practical calculation or have an intuitive understanding of the flux response by means of the modal expansion, in which the solutions are expressed through the eigenvalues and the eigenfunctions.
In the control engineering field, it may be required to get the rough information, such as the equivalent simple lag approximation, rather than the strict or accurate one about the response.
For this reason, the authors tried to get the Green's function of the diffusion equation of the bare, zero power reactor (slab and cylinder-one dimensional) under the specified boundary conditions, in order to get more convenient expressions of the spatial kinetics.
The Green's function also means the transfer function describing the relation between the point neutron source and the neutron flux response.
They approximated this transfer function as the simple rational function of “
s” and discussed its physical meaning. The numerical examples of the strict frequency response of the reactor flux and the dependency on the space variable are shown.
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