CONTEMPT/LT-028 Browns Ferry studies of an anticipated transient without scram

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:5492456

Holcomb, E E

The Browns Ferry Nuclear Plant containment response during the first 30 min of an anticipated transient without scram (ATWS) is the subject of this paper. Three cases, each initiated by a main steam isolation valve closure, are presented: the ATWS is mitigated by operator actions in the spirit of the General Electric Emergency Procedure Guidelines; the ATWS is managed by the plant automatic control systems; and the ATWS proceeds as in first case except that the drywell coolers are unavailable. Success of the standby liquid control system is assumed in the last two transients.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5492456
• Report Number(s): EGG-M-22583; CONF-8310143-42; ON: DE84002207
• Resource Relation: Conference: 11. NRC water reactor safety research information meeting, Gaithersburg, MD, USA, 14 Oct 1983
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ATWS
HEAT TRANSFER
HYDRAULICS
BWR TYPE REACTORS
CONTAINMENT BUILDINGS
COMPUTER CALCULATIONS
PRESSURE GRADIENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
THEORETICAL DATA
ACCIDENTS
CONTAINMENT
DATA
ENERGY TRANSFER
FLUID MECHANICS
INFORMATION
MECHANICS
NUMERICAL DATA
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled