Preliminary analysis of large penetration enclosures for containment vessels subject to beyond design basis loadings

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

OSTI ID:6930716

Kulak, R F; Hsieh, B J; Ash, J E; Kennedy, J M; McLennan, G A

Numerical simulations of the macro-deformations of the sealing surfaces (gasketed junctures) of a PWR steel containment vessel's equipment hatch subjected to accident loadings have been performed. Results for the equipment hatch juncture indicate that the rotations of the hatch cover and penetration sleeve must be accounted for when performing leakage analysis because they can affect the compression of the gasket even though the gasket is in a pressure-seated configuration. Results from a leakage analysis indicated that excessive leakage can occur if the surface roughness is high and/or the compression set is high.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6930716
• Report Number(s): CONF-840913-3; ON: DE84014731
• Resource Relation: Conference: Conference on structural engineering in operating nuclear facilities, Raleigh, NC, USA, 10 Sep 1984; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONTAINMENT BUILDINGS
OPENINGS
SEALS
STRESS ANALYSIS
PWR TYPE REACTORS
LEAKS
DAMAGE
DYNAMIC LOADS
LEAK TESTING
REACTOR ACCIDENTS
ACCIDENTS
BUILDINGS
CONTAINMENT
REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled