Fatigue and environmentally assisted cracking in light water reactors
- 1. Argonne National Lab., IL (United States)
Description
Fatigue and environmentally assisted cracking of piping and pressure vessels in light water reactors (LWRs) are important concerns as extended reactor lifetimes are envisaged. Another concern is failure of reactor-core internal components after accumulation of relatively high fluence, which has occurred in boiling water reactors (BWRs) and pressurized water reactors (PWRs). During this year the work in this program has addressed these concerns: fatigue of ferritic piping and pressure vessel steels, stress corrosion cracking of ferritic steels, effects of water chemistry on stress corrosion cracking of austenitic stainless steels, and irradiation-assisted stress corrosion cracking of Type 304 SS
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Additional details
Publishing Information
- Imprint Title
- Transactions of the nineteenth water reactor safety information meeting
- Imprint Pagination
- 220 p.
- Journal Page Range
- p. 5.5-5.6.
- Report number
- NUREG/CP--0118
Conference
- Title
- 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting.
- Dates
- 28-30 Oct 1991.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059435
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; BWR TYPE REACTORS; CHROMIUM; CRACK PROPAGATION; CRACKS; DATA BASE MANAGEMENT; DYNAMIC LOADS; FATIGUE; FERRITIC STEELS; FRACTURE MECHANICS; NEUTRON FLUENCE; NICKEL; OXYGEN; PHYSICAL RADIATION EFFECTS; PIPES; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RESEARCH PROGRAMS; SERVICE LIFE; STEEL-CR19NI10; STRESS CORROSION; TEMPERATURE DEPENDENCE; THERMAL CYCLING; WATER CHEMISTRY
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHEMISTRY; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CONTAINERS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; ELEMENTS; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LIFETIME; MANAGEMENT; MECHANICAL PROPERTIES; MECHANICS; METALS; NICKEL ALLOYS; NONMETALS; POWER REACTORS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS; SAFETY; STAINLESS STEELS; STEELS; THERMAL REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911079--.