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**Harvard**

Demazière, C., Dykin, V., Hernández-Solís, A. och Boman, V. (2015) *Modelling of stationary fluctuations in nuclear reactor cores in the frequency domain*.

** BibTeX **

@conference{

Demazière2015,

author={Demazière, Christophe and Dykin, Victor and Hernández-Solís, Augusto and Boman, Viktor},

title={Modelling of stationary fluctuations in nuclear reactor cores in the frequency domain},

booktitle={Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, Nashville, United States, 19-23 April 2015},

isbn={978-151080804-1},

abstract={This paper presents the development of a numerical tool to simulate the effect of stationary
fluctuations in Light Water Reactor cores. The originating fluctuations are defined for the variables
describing the boundary conditions of the system, i.e. inlet velocity, inlet enthalpy, and outlet
pressure. The tool calculates the three-dimensional space-frequency distributions within the core of
the corresponding fluctuations in neutron flux, coolant density, coolant velocity, coolant enthalpy,
and fuel temperature. The tool is thus based on the simultaneous modelling of neutron transport,
fluid dynamics, and heat transfer in a truly integrated and fully coupled manner. The modelling of
neutron transport relies on the two-group diffusion approximation and a spatial discretization based
on finite differences. The modelling of fluid dynamics is performed using the homogeneous
equilibrium model complemented with pre-computed static slip ratio. Heat conduction in the fuel
pins is also accounted for, and the heat transfer between the fuel pins and the coolant is modelled
also using a pre-computed distribution of the heat transfer coefficient. The spatial discretization of
the fluid dynamic and heat transfer problems is carried out using finite volumes. The tool is currently
entirely Matlab based with input data provided by an external static core simulator. The paper also
presents the results of dynamic simulations performed for a typical pressurized water reactor and
for a typical boiling water reactor, as illustrations of the capabilities of the tool.},

year={2015},

keywords={LWR multi-physics; noise analysis; neutron transport; fluid dynamics; heat transfer},

}

** RefWorks **

RT Conference Proceedings

SR Print

ID 221829

A1 Demazière, Christophe

A1 Dykin, Victor

A1 Hernández-Solís, Augusto

A1 Boman, Viktor

T1 Modelling of stationary fluctuations in nuclear reactor cores in the frequency domain

YR 2015

T2 Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, Nashville, United States, 19-23 April 2015

SN 978-151080804-1

AB This paper presents the development of a numerical tool to simulate the effect of stationary
fluctuations in Light Water Reactor cores. The originating fluctuations are defined for the variables
describing the boundary conditions of the system, i.e. inlet velocity, inlet enthalpy, and outlet
pressure. The tool calculates the three-dimensional space-frequency distributions within the core of
the corresponding fluctuations in neutron flux, coolant density, coolant velocity, coolant enthalpy,
and fuel temperature. The tool is thus based on the simultaneous modelling of neutron transport,
fluid dynamics, and heat transfer in a truly integrated and fully coupled manner. The modelling of
neutron transport relies on the two-group diffusion approximation and a spatial discretization based
on finite differences. The modelling of fluid dynamics is performed using the homogeneous
equilibrium model complemented with pre-computed static slip ratio. Heat conduction in the fuel
pins is also accounted for, and the heat transfer between the fuel pins and the coolant is modelled
also using a pre-computed distribution of the heat transfer coefficient. The spatial discretization of
the fluid dynamic and heat transfer problems is carried out using finite volumes. The tool is currently
entirely Matlab based with input data provided by an external static core simulator. The paper also
presents the results of dynamic simulations performed for a typical pressurized water reactor and
for a typical boiling water reactor, as illustrations of the capabilities of the tool.

LA eng

OL 30