A survey of computational methods for fluid-structure analysis of reactor safety

The development of computational techniques and computer codes for the analysis of coupled fluid-structure behavior in the field of breeder reactor safety analysis is described. Methods for linear fluid-structure analysis, which are limited to acoustic or small-displacement, incompressible fluids ar...

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Bibliographic Details
Published in:Nuclear engineering and design 1982-05, Vol.69 (3), p.379-398
Main Authors: Kennedy, J.M., Belytschko, T.B.
Format: Article
Language:English
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Summary:The development of computational techniques and computer codes for the analysis of coupled fluid-structure behavior in the field of breeder reactor safety analysis is described. Methods for linear fluid-structure analysis, which are limited to acoustic or small-displacement, incompressible fluids are summarized first. Nonlinear methods have been found necessary for many of the breeder reactor safety problems because large displacements and nonlinear material behavior are encountered. Two problem classes are considered in detail: hypothetical core disruptive accidents, or containment analysis; subassembly analysis. The evolution of codes for these problems is described along with current capabilities and difficulties, and requirements for future developments.
ISSN:0029-5493
1872-759X
DOI:10.1016/0029-5493(82)90185-6