Probability of failure in BWR (Boiling Water Reactor) reactor coolant piping: Volume 2, Pipe failure induced by crack growth and failure of intermediate supports
The US Nuclear Regulatory Commission (NRC) contracted with the Lawrence Livermore National Laboratory (LLNL) to conduct a study to determine if the probability of occurrence of a double-ended guillotine break (DEGB) in the major coolant piping systems of nuclear power plants is large enough to warrant the current stringent design requirements of designing against the postulated effects of a DEGB. The study includes both the PWR (Pressurized Water Reactor) and the BWR (Boiling Water Reactor) plants in the United States. Following the study of PWR plants, a study of BWR reactor coolant piping was performed. The Brunswick Steam Electric Plant at Southport, North Carolina was selected as the pilot plant for the BWR evaluation. The probability of pipe failure in three major coolant pipings was assessed: the recirculation loops, the primary steam lines, and the main feedwater lines. In the case of recirculation loops, both the existing and a proposed replacement system were studied. A probabilistic fracture mechanics approach was used in this study to estimate the crack growth and to assess the crack stability in the piping systems throughout the lifetime of the plant. The effects of the failure of intermediate pipe supports were also examined. The results of the assessment indicated that the probability of occurrence of DEGB due to crack growth and instability is small if the problem of intergranular stress corrosion cracking (IGSCC) is resolved by the use of the replacement system. 33 refs., 41 figs., 32 tabs.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 6163101
- Report Number(s):
- NUREG/CR-4792-Vol.2; UCID-20914-Vol.2; ON: TI89008910
- Country of Publication:
- United States
- Language:
- English
Similar Records
Probability of pipe failure in the reactor coolant loops of Babcock and Wilcox PWR plants. Volume 1. Summary report
Probability of pipe failure in the reactor coolant loops of Combustion Engineering PWR plants. Volume 1. Summary report
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
BWR TYPE REACTORS
REACTOR COOLING SYSTEMS
FAILURES
PROBABILITY
PIPES
PWR TYPE REACTORS
CRACK PROPAGATION
CRACKS
FATIGUE
FRACTURE MECHANICS
FRACTURE PROPERTIES
LEAKS
REACTOR SAFETY
SEISMIC EFFECTS
STAINLESS STEELS
STATISTICS
SUPPORTS
WELDED JOINTS
ALLOYS
COOLING SYSTEMS
ENERGY SYSTEMS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATHEMATICS
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
MECHANICS
REACTOR COMPONENTS
REACTORS
SAFETY
STEELS
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
220900 - Nuclear Reactor Technology- Reactor Safety
990230 - Mathematics & Mathematical Models- (1987-1989)