Archivio Istituzionale della RicercaThis paper is devoted to the physics of a homogeneous fluid-fuel system with perfect remixing. The one-group and multigroup diffusion is firstly adopted. The solution of the space integro-differential eigenvalue equation is obtained by a fully analytical method. Both multiplication and time eigenvalues are determined, and compared with the ones obtained for a standard solid fuel system. The same analytical method is then employed for the solution of the SN problem.
Neutron Diffusion and Transport Problems in Fluid-fuel Reactors / Dulla, Sandra; Prinja, A. K.; Ravetto, Piero. - ELETTRONICO. - (2017). (Intervento presentato al convegno International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering M&C 2017 tenutosi a Jeju, South Korea nel April 2017).
Neutron Diffusion and Transport Problems in Fluid-fuel Reactors
DULLA, SANDRA;RAVETTO, PIERO
2017
Abstract
This paper is devoted to the physics of a homogeneous fluid-fuel system with perfect remixing. The one-group and multigroup diffusion is firstly adopted. The solution of the space integro-differential eigenvalue equation is obtained by a fully analytical method. Both multiplication and time eigenvalues are determined, and compared with the ones obtained for a standard solid fuel system. The same analytical method is then employed for the solution of the SN problem.
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https://hdl.handle.net/11583/2675726
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