Nonlinear finite element analysis of nuclear reinforced prestressed concrete containments up to ultimate load capacity
- Bhabha Atomic Research Centre, Bombay (India). Reactor Engineering Div.
For safety evaluation of nuclear structures a finite element code ULCA (Ultimate Load Capacity Assessment) has been developed. Eight/nine noded isoparametric quadrilateral plate/shell element with reinforcement as a through thickness discrete but integral smeared layer of the element is presented to analyze reinforced and prestressed concrete structures. Various constitutive models such as crushing, cracking in tension, tension stiffening and rebar yielding are studied and effect of these parameters on the reserve strength of structures is brought out through a number of benchmark tests. A global model is used to analyze the prestressed concrete containment wall of a typical 220 MWe Pressurized Heavy Water Reactor (PHWR) up to its ultimate capacity. This demonstrates the adequacy of Indian PHWR containment design to withstand severe accident loads.
- OSTI ID:
- 234303
- Report Number(s):
- CONF-960306-; ISBN 0-7918-1226-X; TRN: IM9624%%344
- Resource Relation:
- Conference: ICONE 4: ASME/JSME international conference on nuclear engineering, New Orleans, LA (United States), 10-13 Mar 1996; Other Information: PBD: 1996; Related Information: Is Part Of ICONE-4: Proceedings. Volume 1 -- Part A: Basic technological advances; Rao, A.S. [ed.] [General Electric Nuclear Energy, San Jose, CA (United States)]; Duffey, R.B. [ed.] [Brookhaven National Lab., Upton, NY (United States)]; Elias, D. [ed.] [Commonwealth Edison, Downers Grove, IL (United States)]; PB: 534 p.
- Country of Publication:
- United States
- Language:
- English
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