New aspects in the implementation of the quasi-static method for the solution of neutron diffusion problems in the framework of a nodal method

Author:

Caron D.,Dulla S.,Ravetto P.

Funder

Accordo di Programma Ministero dello Sviluppo Economico - ENEA sulla Ricerca di Sistema Elettrico

CIRTEN (Consorzio Interuniversitario per la Ricerca Tecnologica Nucleare)

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference16 articles.

1. Bonifetto, R., Caron, D., Dulla, S., Ravetto, P., Savoldi Richard, L., Zanino, R., 2013a. Extension of the FRENETIC code capabilities to the 3D neutronic/thermal-hydraulic dynamic simulation of lead-cooled fast reactors. In: 16th International conference on emerging nuclear energy systems (ICENES 2013), Madrid, 26–30 May 2013.

2. A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors;Bonifetto;Nucl. Eng. Des.,2013

3. Generalized quasi-static method for nuclear reactor space-time kinetics;Devooght;Nucl. Sci. Eng.,1980

4. Effects of neutron source characteristics in direct and adjoint problems for subcritical systems;Dulla;Int. J. Nucl. Energy Sci. Technol.,2006

5. The quasi-static method revisited;Dulla;Prog. Nucl. Energy,2008

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