Ultimate load capacity assessment of reinforced concrete shell structures
Creators
- 1. Bhabha Atomic Research Centre, Bombay (India). Reactor Engineering Div.
Description
The objective of this study is to develop capability for prediction of ultimate load capacity of reinforced concrete shell structures. The present finite element code ULCA (Ultimate Load Capacity Assessment) adopts a degenerate concept of formulating general isoparametric shell element with a layered approach in the thickness direction. Different failure modes such as crushing, tensile cracking and reinforcement yielding are recognised for various problems. The structure fails by crushing of concrete when the concrete strain/stress reaches the ultimate stress or strain of concrete. Material nonlinearities as a result of tension cracking, tension stiffening between reinforcement and concrete in cracked region and yielding of reinforcement are considered along with geometric nonlinearity. Thus with this code it is possible to predict the pressure at which the first cracking, first through thickness cracking, first yielding of reinforcement occurs. After validating the code with few bench mark problems for different failure modes a reinforced concrete nuclear containment is analysed for its ultimate capacity and the results are matched with the published results. Further the ultimate load capacity of outer containment wall of Narora Atomic Power Station is predicted. It is observed that containment fails in membrane region and has a sufficient margin against design pressure. (author). 9 refs., 56 figs., 3 tabs., 1 appendix with 4 tabs
Availability note (English)
MF available from INIS under the Report Number.Files
25047701.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 99 p.
- Report number
- BARC--1993/E/036
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 25047701
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BENCHMARKS; CONTAINMENT SHELLS; CRACKS; FAILURE MODE ANALYSIS; FAILURES; FINITE ELEMENT METHOD; MATHEMATICAL MODELS; NARORA-1 REACTOR; NARORA-2 REACTOR; NONLINEAR PROBLEMS; REINFORCED CONCRETE; SPATIAL DISTRIBUTION; STATIC LOADS; STEELS; STRAINS; STRESSES; TENSILE PROPERTIES; THEORETICAL DATA; U CODES; ULTIMATE STRENGTH
- Descriptors DEC
- ALLOYS; BUILDING MATERIALS; CALCULATION METHODS; CARBON ADDITIONS; COMPOSITE MATERIALS; COMPUTER CODES; CONCRETES; CONTAINMENT; DATA; DISTRIBUTION; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; NATURAL URANIUM REACTORS; NUMERICAL DATA; NUMERICAL SOLUTION; PHWR TYPE REACTORS; POWER REACTORS; REACTORS; REINFORCED MATERIALS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS