Probabilistic assessment of the primary-coolant-loop pipe-fracture due to fatigue crack growth for a PWR plant

Conference · Mon Jun 01 00:00:00 EDT 1981

OSTI ID:6349595

Chou, C K

The work reported herein assesses the probability of a double-ended guillotine break of the hot leg, cold leg and cross-over line (for the purpose of this paper we defined it as a large LOCA) of a PWR plant subjected to the loads caused by plant transients and earthquakes. The work employs a fracture mechanics based fatigue model to propagate cracks from an initial flaw distribution. Flaw size and aspect ratio, material properties, operating transient and seismic stress histories, pre-service and in-service inspections as well as leak defections are considered random variables to be input into the fatigue crack growth fracture mechanics model. A brief description of the model and interrelationship between various steps are discussed.

• Research Organization: Lawrence Livermore National Lab., CA (USA)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 6349595
• Report Number(s): UCRL-86201; CONF-810825-2; ON: TI85016707
• Resource Relation: Conference: Post SMIRT conference, Paris, France, 24 Aug 1981
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
RISK ASSESSMENT
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
SEISMIC EFFECTS
REACTOR MATERIALS
MECHANICAL PROPERTIES
CRACKS
DEFECTS
FRACTURES
PIPES
PROBABILITY
REACTOR SAFETY
SHUTDOWNS
ACCIDENTS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FAILURES
FLUID MECHANICS
MATERIALS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled