Shear strength of end slabs of prestressed concrete nuclear reactor vessels
The report summarizes the experimental and part of the analytical work carried out in connection with an investigation of the structural strength of prestressed concrete reactor vessels. The project is part of the Prestressed Concrete Reactor Vessel Program of the Oak Ridge National Laboratory sponsored by ERDA. The objective of the current phase of the work is to develop procedures to determine the shear strength of flat end slabs of reactor vessels with penetrations.
- Research Organization:
- Illinois Univ., Urbana (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7311103
- Report Number(s):
- ORNL/Sub/4164-1; UILU-ENG-76-2022
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360603 -- Materials-- Properties
BUILDING MATERIALS
CLOSURES
CONCRETES
CONTAINERS
MATERIALS
MECHANICAL PROPERTIES
POWER REACTORS
PRESSURE VESSELS
PRESTRESSED CONCRETE
REACTORS
SHEAR PROPERTIES
SLABS
STRESS ANALYSIS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360603 -- Materials-- Properties
BUILDING MATERIALS
CLOSURES
CONCRETES
CONTAINERS
MATERIALS
MECHANICAL PROPERTIES
POWER REACTORS
PRESSURE VESSELS
PRESTRESSED CONCRETE
REACTORS
SHEAR PROPERTIES
SLABS
STRESS ANALYSIS