Observatorio de I+D+i UPM

Memorias de investigación
Communications at congresses:
Simulation of earthquake sloshing loads in a nuclear reactor
Year:2014
Research Areas
  • Mechanical aeronautics and naval engineering,
  • Civil engineering and architecture
Information
Abstract
Modelling of sloshing flow inside a Lead-cooled Fast Nuclear Reactor during an earthquake is conducted, focusing on the evaluation of the loads caused by the fluid on the structure. AQUAgpusph, a free software OpenCL accelerated SPH code has been used. This tool is analysed, including the performance comparison with some available GPU accelerated SPH codes, and its validation against SPHERIC test case number 10 about severe sloshing phenomena. SPH fits particularly well to this application due to the complex nuclear reactor geometry. Simulations have been conducted with ELSY lead-cooled fast reactor geometry.
International
Si
Congress
9th SPHERIC International Workshop
960
Place
París, Francia
Reviewers
Si
ISBN/ISSN
88-7617-020-0
Start Date
03/06/2014
End Date
05/06/2014
From page
327
To page
334
Session 12 : Real-Life Applications
Participants
  • Autor: Jose Luis Cercos Pita (UPM)
  • Autor: Leo Miguel Gonzalez Gutierrez (UPM)
  • Autor: A. Moreno
  • Autor: A. Guerrero
  • Autor: S. Salgado
Research Group, Departaments and Institutes related
  • Creador: Grupo de Investigación: CEHINAV (Canal de Ensayos Hidrodinámicos de la E.T.S.I. Navales)
  • Departamento: Mecánica de Fluidos y Propulsión Aeroespacial
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