Nonlinear finite element analysis of nuclear reinforced prestressed concrete containments up to ultimate load capacity
Conference
·
OSTI ID:234303
- 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
- Country of Publication:
- United States
- Language:
- English
Similar Records
Ultimate pressure capacity of reinforced and prestressed concrete containments
Review of current analysis methodology for reinforced concrete structural evaluations
Methods for ultimate load analysis of concrete containments
Technical Report
·
Wed May 01 00:00:00 EDT 1985
·
OSTI ID:5682632
Review of current analysis methodology for reinforced concrete structural evaluations
Technical Report
·
Thu Mar 31 23:00:00 EST 1983
·
OSTI ID:5994287
Methods for ultimate load analysis of concrete containments
Technical Report
·
Sat Jun 01 00:00:00 EDT 1985
·
OSTI ID:5630275