1991 EPRI workshop on PWSCC of Alloy 600 in PWRs: Proceedings

Conference · Wed Jul 01 00:00:00 EDT 1992

OSTI ID:7041826

Hunt, E. S.; Gorman, J. A. ^[1]

---

1. Dominion Engineering, Inc., McLean, VA (United States)

A meeting was organized on primary water stress corrosion cracking (PWSCC) of Alloy 600 pressure boundary parts in PWRs to give those working in this area an opportunity to share their experiences, thoughts and plans regarding: The causes of PWSCC in Alloy 600 pressure boundary parts, predictive modelling, strategic planning, inspection methods, repair methods, and possible remedial measures. (VC)

• Research Organization: Electric Power Research Inst., Palo Alto, CA (United States); Dominion Engineering, Inc., McLean, VA (United States)
• Sponsoring Organization: Electric Power Research Inst., Palo Alto, CA (United States)
• OSTI ID: 7041826
• Report Number(s): EPRI-TR--100852; CONF-9110406--
• 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
ABSTRACTS
ALLOY-NI76CR15FE8
ALLOYS
ALUMINIUM ADDITIONS
ALUMINIUM ALLOYS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
COOLING SYSTEMS
CORROSION
CORROSION RESISTANT ALLOYS
CRACKS
DOCUMENT TYPES
ENRICHED URANIUM REACTORS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INCONEL 600
INCONEL ALLOYS
IRON ALLOYS
LEADING ABSTRACT
MATERIALS
MEETINGS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIMONIC
POWER REACTORS
PRESSURIZERS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
STRESS CORROSION
THERMAL REACTORS
TITANIU
TITANIUM ADDITIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS