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An application of the ‘end-point’ method to the minimum critical mass problem in two group transport theory

Authors
Journal
Annals of Nuclear Energy
0306-4549
Publisher
Elsevier
Publication Date
Volume
30
Issue
17
Identifiers
DOI: 10.1016/s0306-4549(03)00135-x

Abstract

Abstract A two group integral equation derived using transport theory, which describes the fuel distribution necessary for a flat thermal flux and minimum critical mass, is solved by the classical end-point method. This method has a number of advantages and in particular highlights the changing behaviour of the fissile mass distribution function in the neighbourhood of the core–reflector interface. We also show how the reflector thermal flux behaves and explain the origin of the maximum which arises when the critical size is less than that corresponding to minimum critical mass. A comparison is made with diffusion theory and the necessary and somewhat artificial presence of surface delta functions in the fuel distribution is shown to be analogous to the edge transients that arise naturally in transport theory.

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