Comparison of analytical and numerical solutions for the multigroup diffusion theory analysis of circulating fuel reactors-Reference-Cited by-同舟云学术

Comparison of analytical and numerical solutions for the multigroup diffusion theory analysis of circulating fuel reactors

Published:2019-10 Issue: Volume:132 Page:636-655
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Ozgener H. Atilla,Ozgener Bilge

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference19 articles.

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3. Neutron diffusion and transport problems in fluid-fuel reactors;Dulla,2017

4. An analysis of discretization for solutions of the diffusion equation using mesh-centered finite differences (I) XYZ geometry;Fletcher;J. Nucl. Sci. Technol.,1998

5. Heimlich A., Santos R., 2011. Macroscopic multigroup constants for accelerator driven system core calculations. In: International Nuclear Atlantic Conference- INAC 2011, Belo, Horizonto, MG, Brazil, October 24-28.

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1. Hydrodynamics coupled circulating-fuel reactor equations in comoving frame and their analytical solutions for molten salt reactors;Nuclear Engineering and Technology;2024-07

2. A positivity-preserving finite volume scheme for multi-group neutron diffusion kinetics equations with delayed neutrons;Computers & Mathematics with Applications;2023-01

3. Numerical and semi-analytical solution of a transient during the start-up of a slab reactor with circulating fuel at zero power;Annals of Nuclear Energy;2021-04