Published 1993
| Version v1
Book
Probabilistic evaluation of ultimate internal pressure capacity of a prestressed concrete containment
Creators
- 1. Korea Power Engineering Company, Inc., Seoul (Korea, Republic of)
- 2. Incheon University, Incheon (Korea, Republic of)
Description
This paper presents the determination of the median ultimate internal pressure capacity of a typical PWR prestressed concrete containment in Korea and the associated variability which represents uncertainties in the median pressure capacity. Failure of the containment is defined as incipient leakage and release of radioactive material into the atmosphere. Leak path and associated area are estimated for controlling failure modes such that the results can be used for evaluating the off-site release probability. (author)
Additional details
Publishing Information
- Publisher
- Elsevier
- Imprint Place
- Amsterdam (Netherlands)
- ISBN
- 0-444-81515-5
- Imprint Title
- Transactions of the 12. international conference on Structural Mechanics in Reactor Technology (SMiRT). Volume M: Structural reliability and Probabilistic Safety Assessment (PSA). Volume N: Decommissioning, waste management and related technologies
- Imprint Pagination
- 382 p.
- Journal Page Range
- p. 13-18
Conference
- Title
- 12. international conference on Structural Mechanics in Reactor Technology
- Acronym
- SMiRT 12
- Dates
- 15-20 Aug 1993
- Place
- Stuttgart (Germany)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36034246
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT BUILDINGS; FISSION PRODUCT RELEASE; LEAK DETECTORS; PRESTRESSED CONCRETE; PROBABILISTIC ESTIMATION; RELEASE LIMITS; RISK ASSESSMENT
- Descriptors DEC
- BUILDING MATERIALS; BUILDINGS; CALCULATION METHODS; COMPOSITE MATERIALS; CONCRETES; CONTAINMENT; MATERIALS
Optional Information
- Notes
- 8 refs, 5 figs