Numerical methods to solve the fuel depletion equations for a nuclear reactor / P.P. Krüger

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dc.contributor.author Krüger, Petrus Paulus
dc.date.accessioned 2009-02-04T08:22:33Z
dc.date.available 2009-02-04T08:22:33Z
dc.date.issued 2004
dc.identifier.uri http://hdl.handle.net/10394/309
dc.description Thesis (M.Sc. (Physics))--North-West University, Potchefstroom Campus, 2004.
dc.description.abstract Different numerical methods for solving the fuel depletion equations in the depletion module of a reactor core analysis system are compared with each other, in order to find the best method and the best implementation of this method to be used in NECSA's OSCAR system. It is assumed that the neutron flux is constant with time over each burnup step, giving a linear system of first order differential equations with constant coefficients that has to be solved. Using the special properties of the fuel depletion equations of stiffness, sparseness and essential-nonnegativity, it is shown how the various methods can be optimally implemented. By using a sample global reactor depletion and an assembly depletion problem, it is then shown that the Taylor expansion method, using a generalised uniformization technique, performs the best under most circumstances.
dc.publisher North-West University
dc.title Numerical methods to solve the fuel depletion equations for a nuclear reactor / P.P. Krüger en
dc.type Thesis en
dc.description.thesistype Masters

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    This collection contains the original digitized versions of research conducted at the North-West University (Potchefstroom Campus)

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