TY - GEN
T1 - Numerical prediction of flow induced vibrations in nuclear reactor applications
AU - Ter Hofstede, E.
AU - Shams, A.
AU - Van Zuijlen, A.
PY - 2015
Y1 - 2015
N2 - Flow induced vibration (FIV) plays an important role in nuclear industry. In nuclear power plants (NPP), FIV may cause fatigue problems, stress corrosion cracking, possible failure modes and fretting wear. In return, this can lead to nuclear safety issues and substantial stand-still costs due to unplanned outage. The demand for an increase in power density of future designs for nuclear reactors often results in the increase of coolant flow velocities or a change of cooling liquid. These changes may alter the flow behavior, which can lead to fluid elastic instability. It is therefore important to asses this phenomenon early in the design process. Most of the experimental studies that have been performed are often simplified or only cover a single operation condition. Numerical methods can play an important role in analyzing complex industrial applications. To gain confidence in the available numerical methods, their validation is an important step that needs to be taken. In the present paper, such a validation study is performed on the used computational methods in Fluid Structure Interaction (FSI) for nuclear plant applications. A partitioned approach is used, in which the exchanges between the fluid and structure solver take place through the use of the Interface Quasi Newton with Inverse Jacobian from a Least Squares (IQN-ILS) coupling scheme. Two different reference databases are used for this validation procedure. The first one is the numerical benchmark case of Turek. In this reference case, the deformation of an elastic flap, attached to a solid cylinder is studied This case is well suited to validate the used coupling methods for applications with large structural deformations, and strong interaction. The second one is an experiment, performed by Vattenfall, where the damping of the flow along an excited (vibrating) slender tube is studied. The results of the simulation of the Vattenfall experiment are preliminary and do not include the coupled simulations.
AB - Flow induced vibration (FIV) plays an important role in nuclear industry. In nuclear power plants (NPP), FIV may cause fatigue problems, stress corrosion cracking, possible failure modes and fretting wear. In return, this can lead to nuclear safety issues and substantial stand-still costs due to unplanned outage. The demand for an increase in power density of future designs for nuclear reactors often results in the increase of coolant flow velocities or a change of cooling liquid. These changes may alter the flow behavior, which can lead to fluid elastic instability. It is therefore important to asses this phenomenon early in the design process. Most of the experimental studies that have been performed are often simplified or only cover a single operation condition. Numerical methods can play an important role in analyzing complex industrial applications. To gain confidence in the available numerical methods, their validation is an important step that needs to be taken. In the present paper, such a validation study is performed on the used computational methods in Fluid Structure Interaction (FSI) for nuclear plant applications. A partitioned approach is used, in which the exchanges between the fluid and structure solver take place through the use of the Interface Quasi Newton with Inverse Jacobian from a Least Squares (IQN-ILS) coupling scheme. Two different reference databases are used for this validation procedure. The first one is the numerical benchmark case of Turek. In this reference case, the deformation of an elastic flap, attached to a solid cylinder is studied This case is well suited to validate the used coupling methods for applications with large structural deformations, and strong interaction. The second one is an experiment, performed by Vattenfall, where the damping of the flow along an excited (vibrating) slender tube is studied. The results of the simulation of the Vattenfall experiment are preliminary and do not include the coupled simulations.
KW - Computational fluid dynamics
KW - Fluid structure interaction
KW - Nuclear reactor
KW - Strong coupling
UR - https://www.scopus.com/pages/publications/84964070307
M3 - Conference contribution
AN - SCOPUS:84964070307
T3 - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
SP - 7725
EP - 7735
BT - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PB - American Nuclear Society
T2 - 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
Y2 - 30 August 2015 through 4 September 2015
ER -