The probability of containment failure by direct containment heating in surry

Technical Report · Mon May 01 04:00:00 EDT 1995

DOI:https://doi.org/10.2172/67788· OSTI ID:67788

Pilch, M M; Allen, M D; Bergeron, K D; Tadios, E L; Stamps, D W ^[1]; Spencer, B W ^[2]; Quick, K S; Knudson, D L ^[3]

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1. Sandia National Labs., Albuquerque, NM (United States)
2. Argonne National Lab., IL (United States)
3. EG and G Idaho, Inc., Idaho Falls, ID (United States)

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.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Technology; Sandia National Labs., Albuquerque, NM (United States); EG and G Idaho, Inc., Idaho Falls, ID (United States); Argonne National Lab., IL (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC04-94AL85000; AC07-94ID13223; W-31109-ENG-38
• OSTI ID: 67788
• Report Number(s): NUREG/CR--6109; SAND--93-2078; ON: TI95012121
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
CONTAINMENT
DESIGN BASIS ACCIDENTS
FAILURES
HEAT TRANSFER
HYDRAULICS
MELTDOWN
PWR TYPE REACTORS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY