Analytical model for shear strength of end slabs of prestressed concrete nuclear reactor vessels

Technical Report · Sun Apr 01 04:00:00 EST 1979

DOI:https://doi.org/10.2172/5837747· OSTI ID:5837747

Abdulrahman, H. O.; Sozen, M. A.; Schnobrich, W. C.

The results are presented of an investigation of the behavior and strength of flat end slabs of cylindrical prestressed concrete nuclear reactor vessels. The investigation included tests of ten small-scale pressure vessels and development of a nonlinear finite-element model to simulate the deformation response and strength of the end slabs. Because earlier experimental studies had shown that the flexural strength of the end slab could be calculated using intelligible procedures, the emphasis of this investigation was on shear strength.

• Research Organization: Illinois Univ., Urbana (USA). Dept. of Civil Engineering
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5837747
• Report Number(s): ORNL/SUB-4164/3; UILU-ENG-78-2026
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360603 -- Materials-- Properties
BUILDING MATERIALS
CONCRETES
CONFIGURATION
CONTAINERS
CYLINDRICAL CONFIGURATION
MATERIALS
MECHANICAL PROPERTIES
PERFORMANCE TESTING
PRESSURE VESSELS
PRESTRESSED CONCRETE
SHEAR PROPERTIES
STRAINS
STRESSES
TESTING