Concrete Reactor Pressure Vessels

This chapter attempts to review the state of the art of methods of analysis and design of the concrete reactor pressure vessels and their components. Existing vessels have been examined for elastic, inelastic and cracking conditions. The results obtained from the analysis given in this chapter and in the appendices are well collaborated with those available for the experimental tests on models and from site monitoring of similar structures of vessels. The text is provided with an up-to-date comprehensive bibliography. 

The state-of-the-art review of the prestressed concrete reactor vessels covers, in this chapter, historical development, the available methods of analysis and design procedures of vessels and their elements such as concrete, prestressing systems, conventional steel, vessel steel liner and anchorages including penetration liners. Each section is presented with a clear-cut discussion on its contents. 

The analytical and design tools thus available in this text have made it possible to investigate fairly accurately the safety margins of other vessels adopted for pressurised water reactors (PWR), boiling water reactors (BWR) and fast breeder reactors (FBR). 

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The literature review and other research has shown that one of the major difficulties In demolishing a prestressed concrete reactor pressure vessel, even 100 years after shutdown, arises from the radiation emitted from the steel components that have become activated during reactor operation. The most effective way of overcoming these difficulties would seem, therefore, to lie In one or more of the following Ideas ... 

The prestressed concrete reactor pressure vessel is 353.3 cm thick... 

Fig. 5.13 Oldbury prestressed concrete reactor pressure vessel...

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