Abstract

In connection with a nuclear reactor, we often need only simple functionals of the solution to the neutron transport equation. Such a functional is the power density distribution or the critical boron concentration. The question of how simple a model can be used to find simple functionals is investigated so that the model is defined as an input- output relation and the model of a model is investigated as an approximation, along with the effects of multiple approximations. As a results, the solution turns out to be poorer in details when more approximations are simultaneously accepted. The problem of error compensation, however, remains to be investigated.

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