Residual stress measurements on sleeves and nozzles
Description
Investigation of the Calvert Cliffs-2 heater sleeve failures confirmed the presence of axial throughwall stress corrosion cracks near the J-weld. It was determined that the primary water stress corrosion cracking (PWSCC), a condition that requires significant tensile stress in order to occur, was caused by a fabrication step which resulted in high residual stresses. In order to quantify these stresses, mock-ups were prepared with four conditions: with weld in reamed area, with weld in non-reamed area, with weld in non-reamed area followed by severe reaming, and in reamed are followed by stress relief. It was concluded that fabricated sleeves in reamed areas away from welds did not have sufficient tensile stresses to initiate PWSCC, J-welds induced high tensile stresses in a circumferential direction on the sleeve sufficient to initiate PWSCC. Reaming permitted development of higher residual stresses because of the presence of a cold worked layer of material and reaming after welding produces compressive stresses which would hinder PWSCC initiation. It was also found that stress relief reduced tensile stresses. 5 figs
Additional details
Publishing Information
- Imprint Title
- 1991 EPRI workshop on PWSCC of Alloy 600 in PWRs: Proceedings
- Imprint Pagination
- 593 p.
- Journal Page Range
- p. E6.1-E6.16.
- Report number
- EPRI-TR--100852
Conference
- Title
- Workshop on primary water stress corrosion cracking (PWSCC) of alloy 600 in PWRs.
- Dates
- 9-11 Oct 1991.
- Place
- Charlotte, NC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24059633
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ALLOY-NI76CR15FE8; COLD WORKING; COMPUTERIZED SIMULATION; HEATERS; NOZZLES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR COMPONENTS; RESIDUAL STRESSES; SLEEVES; STRESS ANALYSIS; STRESS CORROSION; STRESS RELAXATION; WELDED JOINTS
- Descriptors DEC
- ALLOYS; ALUMINIUM ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; FABRICATION; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; JOINTS; MATERIALS WORKING; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; POWER REACTORS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; STRESSES; THERMAL REACTORS; TITANIUM ADDITIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-9110406--.