INEL BWR severe accidnet ATWS study

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

OSTI ID:5492467

Jouse, W C

The subject of this study is a postulate Anticipated Transient Without Scram (ATWS) at unit one of the Browns Ferry nuclear plant, a boiling water reactor (BWR). The development work is being conducted at the Idaho National Engineering Laboratory (INEL) for the U.S. Nuclear Regulatory Commission (NRC). It has long been recognized that the dominant ATWS transient in BWRs is the main steamline isolation valve (MSIV) closure pressurization type of event. The analytic tool used in this study is RELAP5/MOD1.6. This version of RELAP5 has the capability to simulate BWR plants in that several special process models, such as a jet pump momentum mixer model, have been installed.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5492467
• Report Number(s): EGG-M-21583; CONF-8310143-40; ON: DE84002208
• 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
COMPUTER CALCULATIONS
FLOW RATE
PRESSURE GRADIENTS
REACTOR SAFETY
THEORETICAL DATA
ACCIDENTS
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