EPRI research on concrete containment integrity
Creators
Description
A series of research projects concerning the integrity of reactor containment buildings under accident loads that may exceed design levels is underway at the Electric Power Research Institute (EPRI). The objective of the projects is to provide the utility industry with a test-verified analytical method for making realistic estimates of the actual capacity of reinforced and prestressed concrete containments under internal overpressurization and seismic loads. Initial research is focusing on reinforced and prestressed containment response due to quasi-static overpressurization from large- or small-break LOCA's combined with hydrogen burn. Data from large-scale hydrogen burn testing in other EPRI-sponsored research will help define realistic forcing functions for containment structural response. Efforts may be expanded in subsequent years to include the effects of seismic loads
Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Title
- Proceedings of the workshop on containment integrity. Volume I of II
- Journal Page Range
- p. 101-118.
- Report number
- NUREG/CP--0033-Vol.1
Conference
- Title
- Workshop on containment integrity for nuclear power reactors.
- Dates
- 7-9 Jun 1982.
- Place
- Arlington, VA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14775923
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMBUSTION; CONTAINMENT BUILDINGS; DYNAMIC LOADS; FAILURES; HYDROGEN; LOSS OF COOLANT; PRESSURE GRADIENTS; PRESTRESSED CONCRETE; PWR TYPE REACTORS; REACTOR SAFETY; REINFORCED CONCRETE; STRESS ANALYSIS
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; CHEMICAL REACTIONS; COMPOSITE MATERIALS; CONCRETES; CONTAINMENT; ELEMENTS; MATERIALS; NONMETALS; OXIDATION; REACTOR ACCIDENTS; REACTORS; REINFORCED MATERIALS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Portions are illegible in microfiche products.