Proceedings: 1983 workshop on primary-side stress corrosion cracking of PWR steam generator tubing

Conference · Sun Nov 01 04:00:00 EST 1987

OSTI ID:5857619

Stein, A A; McIlree, A R ^[1]

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1. ed.

The 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 on 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)
• OSTI ID: 5857619
• Report Number(s): EPRI-NP-5498; CONF-8311309-; ON: TI88920090
• 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
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
ANNEALING
BOILERS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
COHERENT SCATTERING
COOLING SYSTEMS
CORROSION
CRACK PROPAGATION
CRACKS
CRYSTAL STRUCTURE
DIFFRACTION
ENERGY SYSTEMS
HEAT TREATMENTS
INCONEL 600
INCONEL 690
INCONEL ALLOYS
IRON ALLOYS
LEAKS
MICROSTRUCTURE
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SCATTERING
STEAM GENERATORS
STRESS CORROSION
TUBES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
X-RAY DIFFRACTION