Probability of failure in BWR reactor coolant piping: Probabilistic treatment of stress corrosion cracking in 304 and 316NG BWR piping weldments
The purpose of this report is to describe recent expansions of the previously developed PRAISE code to include recent information to make it more applicable to probabilistic analysis of sensitized weldments in BWR piping. The expansions of PRAISE are concentrated in three areas: (1) probabilistic treatment of stress corrosion crack initiation in 304 and 316NG; (2) probabilistic treatment of residual stresses; and (3) benchmarking with field observations of cracking in 304 BWR piping weldments. This expanded version of PRAISE is called PRAISE-CC, and is a significant extension of earlier versions, which considered only piping failures due to the growth of pre-existing crack-like weld defects. PRAISE-CC retains the earlier PRAISE capabilities.
- Research Organization:
- Failure Analysis Associates, Palo Alto, CA (USA)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 6965463
- Report Number(s):
- NUREG/CR-4792-Vol.3; UCID-20914-Vol.3; ON: TI87003765
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COOLING SYSTEMS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
CRACKS
ENERGY SYSTEMS
FAILURES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PIPES
PROBABILITY
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
REACTORS
STAINLESS STEEL-304
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRESS CORROSION
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COOLING SYSTEMS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
CRACKS
ENERGY SYSTEMS
FAILURES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PIPES
PROBABILITY
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
REACTORS
STAINLESS STEEL-304
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRESS CORROSION
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS