Neutron noise analysis has been done over the decades to predict fuel assembly vibrations and to evaluate safety related issues. Neutron noise occurs due to several reasons: the vibration of the fuel rods, flow obstacles such as rod bending and crud deposition, the moderator temperature and time dependent changes caused by varying flow distributions within a fuel assembly, etc. In order to have a better insight of the neutron noise, a fluid mechanics, structural and neutronics coupled code is developed to perform detailed multiphysics simulations at the level of the fuel rods inside a fuel assembly. In this paper the coupling routine of both steady state and transient calculation is described and the outcome is discussed under several scenarios to understand the influence of rod vibration, moderator temperature and flow distribution on the neutronic field. This paper presents the methodology to couple the multiphysics Computational Fluid Dynamics (CFD) code ANSYS-CFX 16.0 with the 3D neutron diffusion code PARCS v3.0. The model for a 16×16 Pressurized Water Reactor (PWR) fuel assembly is set up for ANSYS-CFX. A sensitivity analysis is carried out to obtain the optimal mesh parameters which results in a good accuracy, as well as a small need for computation capability. Transient cases are studied on a quarter fuel assembly applying oscillating moderator inlet boundary conditions in which the inlet moderator temperature and the inlet moderator velocity are varying over time. In order to simulate the vibration of the fuel rod, the fuel rod part is implemented as immersed solid in ANSYS-CFX. Different vibration modes are applied to both cases: individual single rods of the fuel assembly, and all rods of the fuel assembly. The results of each case are shown in this paper giving a better understanding of how axial power distribution develops with varying flow conditions and vibrating fuel rods.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5786-1
PROCEEDINGS PAPER
Development of a Multiphysics Approach With ANSYS CFX and PARCS for Local Analysis of Neutron Oscillation
Zhuoqi Du,
Zhuoqi Du
Technical University of Munich, Garching, Germany
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Marcus Seidl,
Marcus Seidl
PreussenElektra GmbH, Hannover, Germany
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Rafael Macián-Juan
Rafael Macián-Juan
Technical University of Munich, Garching, Germany
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Zhuoqi Du
Technical University of Munich, Garching, Germany
Marcus Seidl
PreussenElektra GmbH, Hannover, Germany
Rafael Macián-Juan
Technical University of Munich, Garching, Germany
Paper No:
ICONE25-67061, V008T09A038; 9 pages
Published Online:
October 17, 2017
Citation
Du, Z, Seidl, M, & Macián-Juan, R. "Development of a Multiphysics Approach With ANSYS CFX and PARCS for Local Analysis of Neutron Oscillation." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues. Shanghai, China. July 2–6, 2017. V008T09A038. ASME. https://doi.org/10.1115/ICONE25-67061
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