Coupled CFD/CSM vibration design methodology for generation IV long-life fuel and component design. Page: 4 of 20
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Coupled CFD/CSM Vibration Design Methodology for Generation IV
Long-Life Fuel and Component Design
D. P. Weber, S. S. Chen, C. Y. Wang, and T. Y. C. Wei
Reactor Engineering Division
Argonne National Laboratory
Argonne, IL 60439 (USA)
firstname.lastname@example.org; email@example.com; cywang @anl.gov; firstname.lastname@example.org
adapco (Analysis and Design Application Co., Ltd.)
Melville, New York 11747 (USA)
Fluid-structure interaction is a cause of failures experienced in fuel rods and is of particular
importance for all reactor components in Generation IV reactors which unanimously adopt a pool
configuration. A Nuclear Energy Research Initiative (NERI) project proposal has been submitted to
United States Department of Energy (USDOE) to develop an advanced design methodology to
model fluid-structure interaction, predict its consequences, and guide the design of reactor
components. The proposed design methodology is an integrated experimental/theoretical/numerical
technique. Preliminary studies have been performed utilizing the CFD code STAR-CD coupled to a
first-order structural mechanics model to explore the issues of coupled dynamic fluid/structure
interactions - flow field, fluid forces, and instability of tubes - in the cross flow regime. The
coupled tool has been used to predict the characteristics of complex dynamic fluid/structure
interactions. It includes flow field in the wake of a tube or tube array, motion-dependent fluid
forces for a tube, and fluid elastic instability of tube arrays. Specifically, the following calculated
quantities have been compared with published experimental data, (a) Flow Field: flow velocity,
fluid pressure, and fluid forces (steady and fluctuating components) of steady flow across a circular
cylinder at subcritical and critical regions. (b) Fluidelastic Forces: a tube is excited at a given
frequency and amplitude. The resulting flow field and fluid forces acting on the tube are calculated.
(c) Fluidelastic Instability of a Tube Row: coupled vibration of a tube row is analyzed as a function
of flow velocity. Those predicted quantities which have been compared, agree well with
Recent renewed collaborative international interest in the development of nuclear reactor power
plants, which embody the lessons of the current fleet, have focused on the required features of the
Generation IV plants [Carelli 2000, Greenspan 2000}. One of the major desired features of the
Generation IV plants will be proliferation resistance. The common concept behind the design
solutions proposed to incorporate this feature is long-life fuel which reduces tremendously,
refueling needs and the opportunities for diversion. No leakers during a 15 year fuel cycle implies
very tight specifications on fuel rod cladding fretting and wear caused by flow-induced vibrations
during the in-core burn-up period. Vibrations may be caused by axial flow, assembly-to-assembly
and sub-channel to sub-channel cross flow and vortex-shedding, wakes, etc. from fuel bundle
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Weber, D. P.; Chen, S. S.; Wang, C. Y.; Wei, T. Y. C. & Jansson, S. Coupled CFD/CSM vibration design methodology for generation IV long-life fuel and component design., article, June 8, 2000; Illinois. (digital.library.unt.edu/ark:/67531/metadc705916/m1/4/: accessed January 23, 2019), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.