BWRSAR (Boiling Water Reactor Severe Accident Response) calculations of reactor vessel debris pours for Peach Bottom short-term station blackout

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

OSTI ID:6700980

Hodge, S A; Ott, L J

This paper describes recent analyses performed by the BWR Severe Accident Technology (BWRSAT) Program at Oak Ridge National Laboratory to estimate the release of debris from the reactor vessel for the unmitigated short-term station blackout accident sequence. Calculations were performed with the BWR Severe Accident Response (BWRSAR) code and are based upon consideration of the Peach Bottom Atomic Power Station. The modeling strategies employed within BWRSAR for debris relocation within the reactor vessel are briefly discussed and the calculated events of the accident sequence, including details of the calculated debris pours, are presented. 4 refs., 13 figs., 3 tabs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6700980
• Report Number(s): CONF-8810155-12; ON: DE89002319
• Resource Relation: Conference: 16. water reactor safety information meeting, Gaithersburg, MD, USA, 24 Oct 1988; Other Information: Portions of this document 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
PEACH BOTTOM-2 REACTOR
REACTOR ACCIDENTS
PEACH BOTTOM-3 REACTOR
B CODES
BWR TYPE REACTORS
HEAT TRANSFER
HYDRAULICS
NUMERICAL DATA
REACTOR CORES
REACTOR SAFETY
REACTOR VESSELS
ACCIDENTS
COMPUTER CODES
CONTAINERS
DATA
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
INFORMATION
MECHANICS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled