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Nonlinear Analysis of Reactor Vessel & Core Supports Subjected to Accidental Impact Loads

by Quazi A. Hossain, Quadrex Corp, Campbell, CA, USA,
Bimal E. Sarkar, Quadrex Corp, Campbell, CA, USA,
C. C. Tang, Quadrex Corp, Campbell, CA, USA,



Document Type: Proceeding Paper

Part of: Structural Engineering in Nuclear Facilities

Abstract:

Nonlinear dynamic analyses of the reactor vessel, its support systems, the core and the core supports were performed to evaluate the consequences of such drops. Damage was defined in terms of the ductility demand of those critical components where structural failure would damage the fuel rod claddings or result in the dropping of the reactor vessel into the reactor cavity. Finite element models representing the impacted systems were developed to determine the effect of straight and inclined drops. Nonlinear load-deformation characteristics of the major energy-absorbing structural components were determined using incremental analysis. The impact phenomenon was simulated as an initial velocity problem. The applicability of energy-balance method for such multidegree-of-freedom system was examined and the use of a simplified substructuring method has been investigated.

Subject Headings: Dynamic structural analysis | Failure analysis | Nonlinear analysis | Dynamic analysis | Nonlinear response | System analysis | Structural members

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