The probability of containment failure by direct containment heating in surry
Author(s) -
M. Pilch,
Michael D. Allen,
K.D. Bergeron,
E.L. Tadios,
Douglas W. Stamps,
Benjamin Spencer,
K.S. Quick,
D. L. Knudson
Publication year - 1995
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/67788
Subject(s) - boiler blowdown , containment (computer programming) , corium , light water reactor , nuclear engineering , debris , cabin pressurization , reactor pressure vessel , coolant , containment building , waste management , environmental science , exothermic reaction , heat transfer , materials science , accident management , chemistry , engineering , geology , mechanics , mechanical engineering , composite material , inlet , oceanography , physics , organic chemistry , computer science , programming language
In a light-water reactor core melt accident, if the reactor pressure vessel (RPV) fails while the reactor coolant system (RCS) at high pressure, the expulsion of molten core debris may pressurize the reactor containment building (RCB) beyond its failure pressure. A failure in the bottom head of the RPV, followed by melt expulsion and blowdown of the RCS, will entrain molten core debris in the high-velocity steam blowdown gas. This chain of events is called a high-pressure melt ejection (HPME). Four mechanisms may cause a rapid increase in pressure and temperature in the reactor containment: (1) blowdown of the RCS, (2) efficient debris-to-gas heat transfer, (3) exothermic metal-steam and metal-oxygen reactions, and (4) hydrogen combustion. These processes, which lead to increased loads on the containment building, are collectively referred to as direct containment heating (DCH). It is necessary to understand factors that enhance or mitigate DCH because the pressure load imposed on the RCB may lead to early failure of the containment
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