LEAKAGE CHARACTERISTICS OF STEEL CONTAINMENT VESSELS AND THE ANALYSIS OF LEAKAGE RATE DETERMINATIONS

摘要

A primary function of the containment structure, which encloses a nuclear reactor, is the retention of the containment atmosphere in the event of the accidental release of radioactive contaminants from the reactor system. The measure of effectiveness in performing this primary function is directly related to the leak-tightness achieved in the construction of the containment vessel. Absolute leak-tightness cannot be practically attained in large field-erected welded containment structures with numerous penetrations and seals. Leak-tightness is therefore a relative term which dictates the need of establishing a permissible leakage rate commensurate with the conditions which govern the consequences of the escape of a radioactively contaminated atmosphere.