Reactor coolant system depressurization in PWRs with U-tube steam generators

Journal Article · Sat Dec 30 23:00:00 EST 1995 · Transactions of the American Nuclear Society

OSTI ID:411832

Quick, K S; Knudson, D L ^[1]

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1. Idaho National Engineering Lab., Idaho Falls, ID (United States)

Molten core materials could be ejected into the containment building by a high-pressure reactor coolant system (RCS) following reactor vessel failure during certain severe accidents. A rapid rise in containment temperature and pressure, or direct containment heating (DCH), could result from that high-pressure melt ejection (HPME). In an extreme case, the pressurization associated with DCH could lead to containment failure.

• OSTI ID: 411832
• Report Number(s): CONF-951006--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 73; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
CONTAINMENT SYSTEMS
DEPRESSURIZATION
FAILURES
HEATING
HYDRAULICS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
S CODES