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**Harvard**

Jareteg, K., Andersson, R. och Demazière, C. (2015) *Development and test of a transient fine-mesh LWR Multiphysics solver in a CFD Framework*.

** BibTeX **

@conference{

Jareteg2015,

author={Jareteg, Klas and Andersson, Rasmus and Demazière, Christophe},

title={Development and test of a transient fine-mesh LWR Multiphysics solver in a CFD Framework},

booktitle={Proc. Joint Int. Conf. Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method (MC2015)},

isbn={978-0-89448-720-0},

abstract={We present a framework for fine-mesh, transient simulations of coupled neutronics and thermal-
hydraulics for Light Water Reactor (LWR) fuel assemblies. The framework includes models of single-
phase fluid transport for the coolant and conjugate-heat transfer between the coolant and the fuel pins,
complemented by a neutronic solver. The thermal-hydraulic models are based on a CFD approach,
resolving the pressure and velocity coupling via an iterative algorithm. Similarly, the neutronics is for-
mulated in a fine-mesh manner with resolved fuel pins. The neutronic and thermal-hydraulic equations
are discretized and solved in the same numerical framework (foam-extend-3.1). A test case of a quarter
of a fuel pin is used to test the transient behavior of the code for a set of different initial reactivities. The
same geometry is used to simulate a decrease of the inlet temperature, which demonstrates the response
both in the CFD and the neutronics for an increase in reactivity. Furthermore, a system of 7x7 fuel
pins is simulated with the same inlet temperature decrease and we present the temporal development
of the temperature as well as an analysis of the heterogeneities captured by the fine-mesh approach.
The solver is shown to capture the transient multiphysics couplings and demonstrates the numerical and
computational applicability based on the presented cases.},

year={2015},

keywords={Coupled neutronics/thermal-hydraulics, CFD, nuclear reactor multiphysics, transient},

}

** RefWorks **

RT Conference Proceedings

SR Print

ID 221825

A1 Jareteg, Klas

A1 Andersson, Rasmus

A1 Demazière, Christophe

T1 Development and test of a transient fine-mesh LWR Multiphysics solver in a CFD Framework

YR 2015

T2 Proc. Joint Int. Conf. Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method (MC2015)

SN 978-0-89448-720-0

AB We present a framework for fine-mesh, transient simulations of coupled neutronics and thermal-
hydraulics for Light Water Reactor (LWR) fuel assemblies. The framework includes models of single-
phase fluid transport for the coolant and conjugate-heat transfer between the coolant and the fuel pins,
complemented by a neutronic solver. The thermal-hydraulic models are based on a CFD approach,
resolving the pressure and velocity coupling via an iterative algorithm. Similarly, the neutronics is for-
mulated in a fine-mesh manner with resolved fuel pins. The neutronic and thermal-hydraulic equations
are discretized and solved in the same numerical framework (foam-extend-3.1). A test case of a quarter
of a fuel pin is used to test the transient behavior of the code for a set of different initial reactivities. The
same geometry is used to simulate a decrease of the inlet temperature, which demonstrates the response
both in the CFD and the neutronics for an increase in reactivity. Furthermore, a system of 7x7 fuel
pins is simulated with the same inlet temperature decrease and we present the temporal development
of the temperature as well as an analysis of the heterogeneities captured by the fine-mesh approach.
The solver is shown to capture the transient multiphysics couplings and demonstrates the numerical and
computational applicability based on the presented cases.

LA eng

OL 30