Probabilistic risk assessment of filtered-vented containment systems. Mark I BWR
Conference
·
OSTI ID:6475121
This report is concerned with the probabilistic risk assessment of filtered-vented containment systems. (JDB)
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA); Battelle Columbus Labs., OH (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6475121
- Report Number(s):
- SAND-81-0158C; CONF-810606-8; ON: TI85016666
- Country of Publication:
- United States
- Language:
- English
Similar Records
Risk assessment of filtered-vented containment options for a BWR Mark I containment
Risk assessment of filtered-vented containment options for a BWR Mark III containment
An analysis of containment venting as a severe accident mitigation strategy for the BWR Mark II containment
Conference
·
Wed Dec 31 23:00:00 EST 1980
·
OSTI ID:6143398
Risk assessment of filtered-vented containment options for a BWR Mark III containment
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:6827196
An analysis of containment venting as a severe accident mitigation strategy for the BWR Mark II containment
Conference
·
Sat Mar 31 23:00:00 EST 1990
· IEEE Transactions on Nuclear Science (Institute of Electrical and Electronics Engineers); (USA)
·
OSTI ID:6892424
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
CONTAINMENT
CONTAINMENT SYSTEMS
DESIGN
ENGINEERED SAFETY SYSTEMS
FILTERS
OPERATION
PERFORMANCE
PROBABILISTIC ESTIMATION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR OPERATION
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
VENTS
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
CONTAINMENT
CONTAINMENT SYSTEMS
DESIGN
ENGINEERED SAFETY SYSTEMS
FILTERS
OPERATION
PERFORMANCE
PROBABILISTIC ESTIMATION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR OPERATION
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
VENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS