Numerical and semi-analytical solution of a transient during the start-up of a slab reactor with circulating fuel at zero power

Author:

Ozgener Huseyin Atila,Ozgener Bilge

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference20 articles.

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3. Neutron point kinetics model with precursors’ shape function update for molten salt reactor;Diniz;Nucl. Eng. Design,2020

4. Dulla, S., Prinja, A.K., Ravetto, P., 2017. Neutron diffusion and transport problems in fluid-fuel reactors. M&C 2017-International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Jeju, Korea, April 16-20, 2017, on USB. https://www.kns.org/files/int_paper/paper/MC2017_2017_1/P024S01-05DullaS.pdf

5. Neutron kinetics of fluid-fuel systems by the quasi-static method;Dulla;Ann. Nucl. Energy,2004

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1. Kinetics, dynamics, and neutron noise in stationary molten salt reactors;Molten Salt Reactors and Thorium Energy;2024

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