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Abstract

In this context inspection relates to the acceptance of design and construction, and of components that have been in service. Inspection details of the pressure parts of British gas-cooled power reactors is outlined and discussed. Reference is also made to steel containment pressure vessels.

The main problems presented by reactor pressure parts are associated with the large size and also site fabrication. Periodic inspection of plant is restricted to date to those parts that do not emit dangerous radiations. While contamination of the other parts by radioactive dusts introduces another limitation, experience over four years at Calder Hall has shown that components on the heat-exchanger side of the stop valve can be efficiently examined. The need for extension of periodic inspection to the remaining circuit components of gas-cooled nuclear-power plants is emphasized. Reference is made to the need for radical improvement in leak tightness of circuits. Also of the desirability of maintaining simplicity and including essentials only in new specifications or codes of practice for reactor pressure-vessels and circuit components.

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Inspection of Primary Circuits and Reactor Pressure Vessels of Nuclear Power Plant

Abstract

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