Proceedings: 1985 workshop on primary-side stress corrosion cracking of PWR steam generator tubing

Conference · Mon Jun 01 04:00:00 EDT 1987

OSTI ID:5835190

Stein, A A; McIlree, A R ^[1]

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1. ed.

This workshop was held to collect current data on the experience with primary water stress corrosion cracking (PWSCC) of steam generator tubing and the related laboratory investigations. Thirty-two presentations were given covering field experience, correlations of laboratory data to the field, and relationship of material microstructure, stress, and environment to PWSCC. The emphasis of the workshop was more on the fundamentals associated with PWSCC yet culminated with several presentations on remedial measures.

• Research Organization: Stone and Webster Engineering Corp., Boston, MA (USA); Electric Power Research Inst., Palo Alto, CA (USA)
• OSTI ID: 5835190
• Report Number(s): EPRI-NP-5158; CONF-8503284-; ON: TI87920465
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
400400 -- Electrochemistry
ABSTRACTS
ALLOYS
BOILERS
CHEMICAL REACTIONS
CHEMISTRY
CHROMIUM ALLOYS
COOLING SYSTEMS
CORROSION
CRACK PROPAGATION
CRACKS
DOCUMENT TYPES
ELECTROCHEMISTRY
ENERGY SYSTEMS
FRACTURE MECHANICS
HEAT TREATMENTS
INCONEL ALLOYS
LEADING ABSTRACT
MECHANICAL PROPERTIES
MECHANICS
MEETINGS
NICKEL ALLOYS
NICKEL BASE ALLOYS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
STEAM GENERATORS
STRESS CORROSION
TUBES
VAPOR GENERATORS
WATER CHEMISTRY
WATER COOLED REACTORS
WATER MODERATED REACTORS