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EnglishThis 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, S.; Prinja, A. K.; Ravetto, P.. - 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.
| Titolo: | Neutron Diffusion and Transport Problems in Fluid-fuel Reactors | |
| Autori: | ||
| Data di pubblicazione: | 2017 | |
| Abstract: | This paper is devoted to the physics of a homogeneous fluid-fuel system with perfect remixing. Th...e 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. | |
| Appare nelle tipologie: | 4.1 Contributo in Atti di convegno |
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