Analysis of the ultimate structural behaviour of Caorso NPP primary containment
Description
Evaluation of severe accidents in the safety analysis of nuclear power plants requires that the performance of containment structures be analysed with regard to the actual material properties, either the actual strength of as-built structures or the non-linear stress-strain relationship up to failure. In the paper phase I of the study on the ultimate structural behaviour of the Caorso Nuclear Power Plant is described and the results are discussed. The structural analysis was performed using the non-linear computer program ADINA, and the principal result was the high structural capacity of the reinforced concrete structure. The critical structural element proved to be the drywell steel head, which reaches general yielding at about 3.3 times the design pressure. (author). 9 refs, 8 figs, 7 tabs
Additional details
Publishing Information
- Publisher
- IAEA.
- Imprint Place
- Vienna (Austria)
- ISBN
- 92-0-020288-8
- Imprint Title
- Severe accidents in nuclear power plants
- Imprint Pagination
- 772 p.
- Series
- Proceedings series.
- Journal Page Range
- v. 2 p. 301-320.
Conference
- Title
- International symposium on severe accidents in nuclear power plants.
- Dates
- 21-25 Mar 1988.
- Place
- Sorrento (Italy).
INIS
- Country of Publication
- Austria
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 20034822
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; CONTAINMENT BUILDINGS; PRESSURIZATION; REACTOR ACCIDENTS; REINFORCED CONCRETE; STRESS ANALYSIS; SYSTEM FAILURE ANALYSIS
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; BUILDINGS; COMPOSITE MATERIALS; CONCRETES; CONTAINMENT; ENRICHED URANIUM REACTORS; MATERIALS; POWER REACTORS; REACTORS; REINFORCED MATERIALS; SIMULATION; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- IAEA-SM--296/48.