Reactor internals degradation mechanisms
Description
The presentation is centered on the primary stressors for boiling water reactor (BWR) internals, specifically, high temperature and corrosive coolant, sensitized materials, loadings associated with operations, high speed coolant flow, effects of radiation exposure, preloads in bolts and studs, and residual stresses and strains induced by manufacturing processes. Aging-related degradation mechanisms include stress corrosion cracking, fatigue cracking, embrittlement, and erosion. The results of a survey of reported failure cases for specific reactor internal components is presented. A strategy for managing aging-related degradations is presented and includes hydrogen water chemistry management, strengthening of structural components, reducing potential for flow-induced vibration, and improvement of detection and inspection methods
Additional details
Publishing Information
- Imprint Title
- Eighteenth water reactor safety information meeting. Volume 3, Pressure vessel integrity; Piping and NDE; Aging and components: Proceedings
- Imprint Pagination
- 574 p.
- Journal Page Range
- p. 453-484.
- Report number
- NUREG/CP--0114-Vol.3
Conference
- Title
- 18. water reactor safety information meeting.
- Dates
- 22-24 Oct 1990.
- Place
- Rockville, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24038763
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; BWR TYPE REACTORS; CHROMIUM; CONTROL ROD DRIVES; CORE SPRAY SYSTEMS; CORROSION; CRACK PROPAGATION; CRACKS; DROPLETS; DRYERS; EFFICIENCY; EMBRITTLEMENT; ENGINEERED SAFETY SYSTEMS; EPRI; EROSION; FAILURES; FASTENERS; FATIGUE; FLUID-STRUCTURE INTERACTIONS; GRAIN BOUNDARIES; GUIDE TUBES; HEAT TRANSFER; IN CORE INSTRUMENTS; INSPECTION; INTERGRANULAR CORROSION; JACKETS; MITIGATION; NEUTRON FLUX; NEUTRON SOURCES; PHYSICAL RADIATION EFFECTS; PUMPS; REACTOR COMPONENTS; REACTOR CONTROL SYSTEMS; REACTOR CORES; REACTOR MONITORING SYSTEMS; REACTOR OPERATION; RESIDUAL STRESSES; STEEL-CR19NI10; STRESS CORROSION; SUPPORTS; TENSILE PROPERTIES; THERMAL CYCLING; TWO-PHASE FLOW; WATER CHEMISTRY
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHEMISTRY; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CONTROL SYSTEMS; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; ECCS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLUID FLOW; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; MECHANICAL STRUCTURES; METALS; MICROSTRUCTURE; NICKEL ALLOYS; OPERATION; PARTICLE SOURCES; PARTICLES; POWER REACTORS; RADIATION EFFECTS; RADIATION FLUX; RADIATION SOURCES; REACTOR PROTECTION SYSTEMS; REACTORS; STAINLESS STEELS; STEELS; STRESSES; THERMAL REACTORS; TRANSITION ELEMENTS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400
- Secondary number(s)
- CONF-9010185--Vol.3.