An attempt has been made to explain the advan-tages of the behavior of prestressed concrete reactor vessels in a simple, brief, and qualitative form. In contrast to the property of spontaneous propagation of brittle fracture in massive steel plates. the failure of one prestressing wire or tendon does not propagate into the adjacent wires or tendons. The pressure-deflection curve does not end by a sudden failure, but the decrease of slope on approach to failure is gradual and even after formation of through cracks the vessel would close if depressurized. The energy absorption capability in post-elastic deformation is much higher than that of a steel vessel which could fail by brittle fracture. A weak part is the top closure slab, but if it i...
An analytical model of a prestressed concrete reactor vessel (pCR V) for LMFBR ilnd the associated f...
This report is concerned with the analysis and its' review of a prestresied concrete reactor vessel ...
International audienceIn high-power French nuclear power plants (1300 and 1450 MWe), the concrete co...
This lecture reviews new developments in analysis and design of prestressed concrete reactor vessels...
Reported are preliminary results of a study at the Argonne National laboratory, the objective of whi...
International audienceThe Gas cooled Fast Reactor (GFR) is considered by the French Commissariat à l...
A nuclear power plant is provided with an extensive defense intended to prevent radioactive discharg...
Presently for gas-cooled reactors prestressed concrete vessels made of prestressed concrete are inse...
A Report on an Investigation carried out as part of the Prestressed Concrete Reactor Vessel Program ...
Thesis. 1975. M.S.--Massachusetts Institute of Technology. Dept. of Civil Engineering.Bibliography: ...
Determining the durability of a reactor vessel requires a hygro-thermo-mechanical analysis of the ve...
A safety analysis for a nuclear reactor pressure vessel based on linear elastic fracture mechanics c...
Two single-cavity prestressed concrete reactor vessel (PCRV) models were fabricated and tested to fa...
The magnitude of pore pressures and the loss of moisture caused by heating of concrete is of conside...
Reduced prestressing and degradation of prestressing tendons in concrete containment vessels were in...
An analytical model of a prestressed concrete reactor vessel (pCR V) for LMFBR ilnd the associated f...
This report is concerned with the analysis and its' review of a prestresied concrete reactor vessel ...
International audienceIn high-power French nuclear power plants (1300 and 1450 MWe), the concrete co...
This lecture reviews new developments in analysis and design of prestressed concrete reactor vessels...
Reported are preliminary results of a study at the Argonne National laboratory, the objective of whi...
International audienceThe Gas cooled Fast Reactor (GFR) is considered by the French Commissariat à l...
A nuclear power plant is provided with an extensive defense intended to prevent radioactive discharg...
Presently for gas-cooled reactors prestressed concrete vessels made of prestressed concrete are inse...
A Report on an Investigation carried out as part of the Prestressed Concrete Reactor Vessel Program ...
Thesis. 1975. M.S.--Massachusetts Institute of Technology. Dept. of Civil Engineering.Bibliography: ...
Determining the durability of a reactor vessel requires a hygro-thermo-mechanical analysis of the ve...
A safety analysis for a nuclear reactor pressure vessel based on linear elastic fracture mechanics c...
Two single-cavity prestressed concrete reactor vessel (PCRV) models were fabricated and tested to fa...
The magnitude of pore pressures and the loss of moisture caused by heating of concrete is of conside...
Reduced prestressing and degradation of prestressing tendons in concrete containment vessels were in...
An analytical model of a prestressed concrete reactor vessel (pCR V) for LMFBR ilnd the associated f...
This report is concerned with the analysis and its' review of a prestresied concrete reactor vessel ...
International audienceIn high-power French nuclear power plants (1300 and 1450 MWe), the concrete co...