An analysis of risk reduction methods for interfacing system LOCAs at PWRs
Conference
·
OSTI ID:5226322
Interfacing system loss-of-coolant accidents (ISLs) refers to events where the integrity of the Reactor Coolant System (RCS) pressure boundary is breached through failure of isolation valves which separate a support system of lower design pressure. The overpressurization of the support system will affect its availability and may further affect the availability of various safety systems required to mitigate the accident. In addition, it may result in a scenario where primary coolant is directly discharged into the outside environment by passing the containment. The Reactor Safety Study (WASH-1400) predicted that ISL events were significant contributors to risk even though they were calculated to be relatively low frequency events. However, there are substantial uncertain involved in determining the probability and consequences of the ISL sequences. For example, the assumed valve failure modes, common cause contributions and the location of the break/leak are all uncertain and can significantly influence the predicted risk from ISL events. The present study was performed to investigate the vulnerability of pressurized water reactor designs to ISLs and identify any improvements that could significantly reduce the frequency of these events.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5226322
- Report Number(s):
- BNL-NUREG-40756; CONF-880601-15; ON: DE88006295
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis of risk reduction methods for interfacing system LOCAs (loss-of-coolant accidents) at PWRs
PWR (Pressurized Water Reactor) interfacing system LOCAs (loss-of-coolant accidents): Analysis of risk reduction alternatives
Recent advances in analysis of PWR containment bypass accidents
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:6968283
PWR (Pressurized Water Reactor) interfacing system LOCAs (loss-of-coolant accidents): Analysis of risk reduction alternatives
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:6417402
Recent advances in analysis of PWR containment bypass accidents
Conference
·
Mon Dec 31 23:00:00 EST 1990
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5763353
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LEAK TESTING
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
TESTING
VALUES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LEAK TESTING
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
TESTING
VALUES
WATER COOLED REACTORS
WATER MODERATED REACTORS