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Parametric Study of Radioactive Release from a Breached Containment

A. Kenigsberg, D. Hasan, E. Elias

Nuclear Technology

Volume 50 / Number 3 / October 1980 / Pages 219-224


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A hypothetical accident is analyzed, in which an external (outof-plant) natural or man-made event causes a loss-of-coolant accident after penetrating the containment wall The computer codes CONTEMPT and RELAP4 have been used to study the containment thermal-hydraulic behavior during the accident. The radioactive materials outflow rate is calculated for a wide range of anticipated breach sizes, assuming perfect mixing in the air-steam-water mixture in the containment building. Typically, there is only a low pressure buildup in the initially breached containment. Therefore, the calculated fission product release rate is lower than the predicted rate in case the containment fractures in a later phase of the accident.

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