Proceedings: Primary water stress corrosion cracking: 1989 EPRI remedial measures workshop

Conference · Sun Apr 01 00:00:00 EST 1990

OSTI ID:6928117

Gorman, J A ^[1]

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1. Dominion Engineering, Inc., McLean, VA (USA)

A meeting on PWSCC Remedial Measures'' was organized to give those working in this area an opportunity to share their results, ideas and plans with regard to development and application of remedial measures directed against the primary water stress corrosion cracking (PWSCC) phenomenon affecting alloy 600 steam generator tubes. Topics discussed included: utility experience and strategies; nondestructive examination (NDE) methods for PWSCC; technical topics ranging from predictive methods for occurrence of PWSCC to results of corrosion tests; and services provided by vendors that can help prevent the occurrence of PWSCC or can help address problems caused by PWSCC once it occurs.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (USA); Dominion Engineering, Inc., McLean, VA (USA)
• Sponsoring Organization: EPRI
• OSTI ID: 6928117
• Report Number(s): EPRI-NP-6719-M; CONF-8902179-Summ.; TRN: 90-018208
• Resource Relation: Conference: EPRI remedial measures workshop, Clearwater Beach, FL (USA), 8-10 Feb 1989
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
NUCLEAR POWER PLANTS
STEAM GENERATORS
STRESS CORROSION
REMEDIAL ACTION
INCONEL ALLOYS
NONDESTRUCTIVE ANALYSIS
PRIMARY COOLANT CIRCUITS
RELIABILITY
SLEEVES
STRESS RELAXATION
TUBES
ALLOYS
BOILERS
CHEMICAL ANALYSIS
CHEMICAL REACTIONS
COOLING SYSTEMS
CORROSION
ENERGY SYSTEMS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NUCLEAR FACILITIES
POWER PLANTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
RELAXATION
THERMAL POWER PLANTS
VAPOR GENERATORS
220200* - Nuclear Reactor Technology- Components & Accessories
360105 - Metals & Alloys- Corrosion & Erosion