U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1 Page: 1-44
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ORIEL D:. 6a-
Fig. 1.10. High-Pressure Containment Shown with Pressurized-Water,
Gas-Cooled, or Organic-Cooled Reactors.
In any event the leakage rate from a pressure-containment system is
usually held to a small fraction of the contained volume; the maximum
permissible leakage rate is a function of the reactor site and the activity
released from the reactor system. Pressure containment is commonly em-
ployed for the pressurized-water and boiling-water reactors where large
volumes of the pressurized coolant may be released by the accident con-
current with or soon followed by large amounts of activity. This form
of containment was the earliest developed and therefore has also been
used on several other reactor systems.
1.4.2 Pressure-Suppression Containment
Pressure-suppression (or, as it is sometimes called, vapor-condensa-
tion) containment is based on deposition of the energy resulting from a
reactor by condensing the vapor in a pool of water as it is released.
Obviously this technique is only applicable to reactor accidents that re-
lease a condensable vapor, such as steam. The pressure-suppression con-
tainment system shown schematically in Fig. 1.11 is composed of two main
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Cottrell, William B. & Savolainen, A. W. U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1, report, August 1965; Oak Ridge, Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc101033/m1/72/: accessed March 25, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.