Displaying similar documents to “Criticality conditions for a finite homogenized natural-uranium fueled reactor with prescribed thermal neutron flux”

A sufficient condition for flattening of the thermal neutron flux and some related problems (in onedimensional geometries)

Rostislav Zezula (1969)

Aplikace matematiky

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The main results of this paper, in which the problem of determination of the fuel concentration distribution M inducing a prescribed thermal neutron flux Φ in the homogenized critical reactor core with given outer reflector boundary is investigated (in the two-groups diffusion approximation), are stated in the theorems 1 and 2. In theorem 1 sufficient conditions are given for the existence of a oneparametrical family of thermal neutron fluxes induced by the Goertzel’s type fuel concentration...

The output least squares identifiability of the diffusion coefficient from an H 1 –observation in a 2–D elliptic equation

Guy Chavent, Karl Kunisch (2002)

ESAIM: Control, Optimisation and Calculus of Variations

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Output least squares stability for the diffusion coefficient in an elliptic equation in dimension two is analyzed. This guarantees Lipschitz stability of the solution of the least squares formulation with respect to perturbations in the data independently of their attainability. The analysis shows the influence of the flow direction on the parameter to be estimated. A scale analysis for multi-scale resolution of the unknown parameter is provided.