Probabilistic analyses of failure in reactor coolant piping. [Double-ended guillotine break]

Conference · Fri Jul 20 00:00:00 EDT 1984

OSTI ID:6622410

Holman, G S

LLNL is performing probabilistic reliability analyses of PWR and BWR reactor coolant piping for the NRC Office of Nuclear Regulatory Research. Specifically, LLNL is estimating the probability of a double-ended guillotine break (DEGB) in the reactor coolant loop piping in PWR plants, and in the main stream, feedwater, and recirculation piping of BWR plants. In estimating the probability of DEGB, LLNL considers two causes of pipe break: pipe fracture due to the growth of cracks at welded joints (direct DEGB), and pipe rupture indirectly caused by the seismically-induced failure of critical supports or equipment (indirect DEGB).

• Research Organization: Lawrence Livermore National Lab., CA (USA)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 6622410
• Report Number(s): UCRL-91292; CONF-840763-4; ON: DE84015600
• Resource Relation: Conference: MITI-USNRC seismic information exchange meeting, Palo Alto, CA, USA, 18 Jul 1984
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
LOSS OF COOLANT
PROBABILITY
PWR TYPE REACTORS
EARTHQUAKES
FAILURES
FEEDWATER
PIPES
REACTOR COOLING SYSTEMS
RELIABILITY
RUPTURES
SEISMIC EFFECTS
STEAM LINES
SUPPORTS
ACCIDENTS
COOLING SYSTEMS
ENERGY SYSTEMS
HYDROGEN COMPOUNDS
MECHANICAL STRUCTURES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SEISMIC EVENTS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled