Containment leakage during severe accident conditions

Conference · Sun Jan 01 00:00:00 EST 1984

OSTI ID:6409677

Hofmayer, C H; Bagchi, G; Noonan, V S

An alternate to the THRESHOLD model used in most severe accident risk assessments has been investigated. One reference plant for each of six containment types has been studied to determine the magnitude of containment leakage that would result from the pressures and temperatures associated with severe accident conditions. Containment penetrations having the greatest potential for early containment leakage are identified. The studies indicate that containment leakage through penetrations prior to reaching containment threshold pressures (currently reported containment shell failure pressures) should be considered in severe accident risk assessments. Failure of non-metallic seals for containment penetrations can be a significant source of containment leakage under severe accident pressure and temperature conditions. Although studies of containment types are useful in identifying sources of containment leakage, final conclusions may need to be plant specific. Recommendations concerning future studies to better develop the use of continuous leakage models are provided. 9 references, 4 figures, 2 tables.

• Research Organization: Brookhaven National Lab., Upton, NY (USA); Nuclear Regulatory Commission, Washington, DC (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6409677
• Report Number(s): BNL-NUREG-35286; CONF-8406124-13; ON: TI85000892; TRN: 85-000137
• Resource Relation: Conference: 2. workshop on containment integrity, Crystal City, VA, USA, 13 Jun 1984
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
CONTAINMENT SYSTEMS
LEAKS
NUCLEAR POWER PLANTS
REACTOR ACCIDENTS
FAILURES
PRESSURE EFFECTS
RISK ASSESSMENT
SEALS
TEMPERATURE EFFECTS
ACCIDENTS
CONTAINMENT
ENGINEERED SAFETY SYSTEMS
NUCLEAR FACILITIES
POWER PLANTS
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety