On the time-dependent flux distribution of a fixed-full thermal nuclear reactor
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An analytical method is presented for determining the flux distribution and reactivity in a bare homogeneous thermal nuclear reactor during fuel burn-up. It is shown that these two functions can, in principle, be calculated from a recursive set of differential equations. The analysis is illustrated for the case of a flat plate reactor.
KeywordsFlux Distribution Fission Cross Section Flux Time Nuclide Concentration Thermal Diffusion Equation
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