Systemic-event tree methodology employed in the interim reliability evaluation program (IREP). [PWR; BWR]
Conference
·
OSTI ID:5983451
This paper summarizes the systemic event tree methodology employed in the IREP. The analysis steps required to construct a set of event trees which model core meltdown accident sequences initiated by a variety of LOCA and transient initiating events are discussed. Analysis of the emergency procedures the plant operators follow during a given accident sequence is also discussed.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5983451
- Report Number(s):
- SAND-81-2073C; CONF-810905-19; ON: DE81030719
- Country of Publication:
- United States
- Language:
- English
Similar Records
Interim reliability evaluation program (IREP)
Interim reliability evaluation program: analysis of the Arkansas Nuclear One. Unit 1 Nuclear Power Plant
Interim reliability-evaluation program: analysis of the Millstone Point Unit 1 nuclear power plant. Volume I. Main report
Conference
·
Wed Dec 31 23:00:00 EST 1980
·
OSTI ID:5816682
Interim reliability evaluation program: analysis of the Arkansas Nuclear One. Unit 1 Nuclear Power Plant
Technical Report
·
Tue Jun 01 00:00:00 EDT 1982
·
OSTI ID:5059651
Interim reliability-evaluation program: analysis of the Millstone Point Unit 1 nuclear power plant. Volume I. Main report
Technical Report
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:6345027
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
FAILURE MODE ANALYSIS
LOSS OF COOLANT
MELTDOWN
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RELIABILITY
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
FAILURE MODE ANALYSIS
LOSS OF COOLANT
MELTDOWN
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RELIABILITY
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS