Parametric contain calculations of the containment response of the Grand Gulf plant due to reactor pressure vessel failure at high pressure

Conference · Fri Jan 01 00:00:00 EST 1988

OSTI ID:7037362

Murata, K K; Louie, D L.Y.

A parametric study of the containment response of the Grand Gulf plant, a Mark III BWR, has been conducted using the Contain code. The response to extensive debris dispersal following reactor pressure vessel failure at high pressure is examined for a short period after vessel failure, for plant conditions corresponding to a short-term station blackout scenario with water on the floor of the drywell. The discussion of results from this study focuses on the peak drywell-wetwell pressure difference, the peak pedestal pressure, and the potential for drywell flooding after debris dispersal.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 7037362
• Report Number(s): SAND-88-1612C; CONF-880616-3; ON: DE88012334; TRN: 88-025175
• Resource Relation: Conference: 4. workshop on integrity of containments for nuclear power plants, Washington, DC, USA, 15 Jun 1988; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
PRESSURE VESSELS
FAILURES
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINMENT SYSTEMS
CONTAINERS
CONTAINMENT
ENGINEERED SAFETY SYSTEMS
REACTORS
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled