Air Ingress to Internal Concrete Members of a Reactor Containment Building During Leakage Rate Tests

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Title: Air Ingress to Internal Concrete Members of a Reactor Containment Building During Leakage Rate Tests

Author(s): Mostafa Toossi

Publication: Journal Proceedings

Volume: 81

Issue: 1

Appears on pages(s): 69-72

Keywords: air; premeability; pressure; nuclear reactor containment; reinforced concrete; seepage; tests; void-cement ratio.

Date: 1/1/1984

Abstract:
A method for evaluating the amount of air ingested in the internal concrete of a nuclear reactor building during leakage test is presented. The evaluation is based on an examination of important parameters such as concrete void ratio, exposed area, and its permeability. The volume of air ingested in the internal concrete of a 600 HWe CANDU-type reactor building is calculated. The results show that the contribution of air ingestion phenomeon to the air pressure drop during the leakage rate test is not negligible.