The integration of thermal-hydraulics (CFD) and structural analysis (FEM) computer codes in liquid and solid mechanics (MULTIPHYSICS)

    Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

    Abstract

    The main objective of the project is to improve modeling capabilities in fluid-structure-interaction (FSI) systems. Because FSI -problems are very common in industry, there is a need to develop simulation tools for these problems. An important application in nuclear industry is the structural integrity of nuclear reactor core internals in Design Basis Accident (DBA). The specific case studied in the project is Large Break Loss of Coolant Accident (LBLOCA) and especially the pressure transient, which is caused by the guillotine pipe break in LBLOCA. Tools planned to be used for the analysis are computational fluid dynamics (CFD) and finite element stress and strain analysis (FEA) codes. An original aim of the project was to study the possibility to develop a common numerical model for system geometry with suitable meshing for all physical analysis disciplines, including both CFD and FEA modeling. However, quite soon the target proved to be unrealistic. The common meshing would decrease the quality of both analyses too much. In the next phase the target was set on separate calculation of the pressure transient with CFD and FEA codes and also on development of the method, which could link CFD and FEA calculation results through interpolation. Firstly, one way coupling between CFD and FEA has been tested, but the final goal is to use a two way link. The codes used in this work are NASTRAN and ABAQUS on the FEA side and STAR-CD in the CFD side. In this paper separate pressure transient calculations using CFD and FEA codes in LBLOCA case are presented. The case has been calculated separately with NASTRAN and STAR-CD. Also one way link between STAR-CD and ABAQUS is tested.
    Original languageEnglish
    Title of host publicationSAFIR, The Finnish Research Programme on Nuclear Power Plant Safety 2003 - 2006
    Subtitle of host publicationInterim Report
    Place of PublicationEspoo
    PublisherVTT Technical Research Centre of Finland
    Pages124-131
    ISBN (Electronic)951-38-6516-9
    ISBN (Print)951-38-6515-0
    Publication statusPublished - 2004
    MoE publication typeD2 Article in professional manuals or guides or professional information systems or text book material

    Publication series

    SeriesVTT Tiedotteita - Research Notes
    Number2272
    ISSN1235-0605

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