A multi-dimensional arbitrary Lagrangian-Eulerian method for dynamic fluid-structure interaction

Conference · Fri Jan 01 00:00:00 EST 1982 · Am. Soc. Mech. Eng., Pressure Vessels Piping Div., (Tech. Rep.) PVP; (United States)

OSTI ID:5658894

This paper describes an arbitrary Lagrangian-Eulerian method for analyzing fluid-structure interactions in fast reactor containment with complex internal structures. In the analysis the fluid transient can be calculated either implicitly or explicitly, using a finite-difference mesh with vertices that may be moved with the fluid (Lagrangian), held fixed (Eulerian), or moved in any other prescribed manner (hybrid Lagrangian-Eulerian). The structural response is computed explicitly by two nonlinear, elastic-plastic finite element modules formulated in corotational coordinates. Interaction between fluid and structure is accounted for by enforcing the interface boundary conditions. The method has convincing advantages in treating complicated phenomena such as flow through perforated structures, large material distortions, flow around corners and irregularities, and highly contorted fluid boundaries. Several sample problems are given to illustrate the effectiveness of this arbitrary Lagrangian-Eulerian method.

• Research Organization: Argonne National Laboratory, Argonne, IL
• OSTI ID: 5658894
• Report Number(s): CONF-820601-; TRN: 84-000085
• Journal Information: Am. Soc. Mech. Eng., Pressure Vessels Piping Div., (Tech. Rep.) PVP; (United States), Vol. PVP-VOL. 64; Conference: ASME pressure vessel and piping conference, Orlando, FL, USA, 27 Jun 1982
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
FAST REACTORS
FLUID-STRUCTURE INTERACTIONS
LAGRANGIAN FUNCTION
BOUNDARY CONDITIONS
CONTAINMENT
DYNAMICS
ELASTICITY
FINITE DIFFERENCE METHOD
MESH GENERATION
PERFORATION
PLASTICITY
TRANSIENTS
EPITHERMAL REACTORS
FUNCTIONS
ITERATIVE METHODS
MECHANICAL PROPERTIES
MECHANICS
NUMERICAL SOLUTION
REACTORS
TENSILE PROPERTIES
210000* - Nuclear Power Plants
420400 - Engineering- Heat Transfer & Fluid Flow