Concrete containment tests: Phase 2, Structural elements with liner plates: Interim report
The tests described in this report are part of Phase 2 of the Electric Power Research Institute (EPRI) program. The overall objective of the EPRI program is to provide a test-verified analytical method of estimating capacities of concrete reactor containment buildings under internal overpressurization from postulated degraded core accidents. The Phase 2 testing included seven large-scale specimens representing structural elements from reinforced and prestressed concrete reactor containment buildings. Six of the seven test specimens were square wall elements. Of these six specimens, four were used for biaxial tension tests to determine strength, deformation, and leak-rate characteristics of full-scale wall elements representing prestressed concrete containment design. The remaining two square wall elements were used for thermal buckling tests to determine whether buckling of the steel liner plate would occur between anchorages when subjected to a sudden extreme temperature differential. The last of the seven test specimens for Phase 2 represented the region where the wall and the basemat intersect in a prestressed concrete containment building. A multi-directional loading scheme was used to produce high bending moments and shear in the wall/basemat junction region. The objective of this test was to determine if there is potential for liner plate tearing in the junction region. Results presented include observed behavior and extensive measurements of deformations and strains as a function of applied load. The data are being used to confirm analytical models for predicting strength and deformation of containment structures in a separate parallel analytical investigation sponsored by EPRI.
- Research Organization:
- Construction Technology Labs., Skokie, IL (USA); Electric Power Research Inst., Palo Alto, CA (USA)
- OSTI ID:
- 6299904
- Report Number(s):
- EPRI-NP-4867M; ON: TI87920560
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360603 -- Materials-- Properties
ACCIDENTS
ALLOYS
BUILDING MATERIALS
BUILDINGS
CONCRETES
CONTAINMENT
CRACK PROPAGATION
CRACKS
IRON ALLOYS
IRON BASE ALLOYS
LINERS
MATERIALS
MECHANICAL STRUCTURES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PRESSURE GRADIENTS
PRESTRESSED CONCRETE
REACTOR ACCIDENTS
REINFORCED CONCRETE
REINFORCED MATERIALS
STEELS
TESTING
THERMAL POWER PLANTS