Measurements and CFD Predictions of Velocity, Turbulence Intensity and Pressure Development in BWR Fuel Rod Assembly with Spacers
2007 (English)In: Proceedings of the 12th International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH12), 2007Conference paper (Refereed)
The current paper presents measurements of axial velocity and its fluctuating component across a spacer in a rod bundle, using LDV technique. The measurements were performed in single-phase water flow in three subchannels of an asymmetric 24-rod mock-up of SVEA-96 fuel bundle. The subchannels differ in the spacer part. CFD models of the three subchannels were developed using commercial CFX 10.0 code. The flow structure in the spacer region has been predicted with two different turbulence models available in the code. The predictions were compared to the current experiments and additionally to experiments of pressure distribution across the spacer reported previously. The comparison showed that CFX code could predict the pressure drop over the spacer with an accuracy of 20-30%. The axial velocity development in the middle point of the subchannel could be reasonably predicted. However, the turbulence intensity increase downstream the spacer observed in the experiments could not be adequately predicted by the chosen turbulence models.
Place, publisher, year, edition, pages
Rod bundle, spacer, experimental flow characteristics, CFD
IdentifiersURN: urn:nbn:se:kth:diva-9905ScopusID: 2-s2.0-44349123025ISBN: 978-089448058-4OAI: oai:DiVA.org:kth-9905DiVA: diva2:158036
The 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), Sheraton Station Square, Pittsburgh, Pennsylvania, U.S.A. September 30-October 4, 2007.
QC 201010072009-02-182009-01-292014-11-07Bibliographically approved