Influence of lead on the SCC-behaviour of SG tubing materials
Creators
Description
All Siemens/KWU designed PWRs use Alloy 800 mod. as SG tubing material. Till now, no IGA/IGSCC has been observed in these plants. Replacement SGs offered by Siemens/KWU in Europe for plants of other NSSS-vendors may use Alloy 690 TT as SG tubing material. Specific questions of PWR operators induced test series on the corrosion behaviour of Alloy 800 mod. and Alloy 690 TT under highly faulted chemistry conditions. One of the test series was performed in order to clarify the influence of lead contamination on the SCC-behaviour of Alloy 800 mod. and Alloy 690 TT. The objective of the test run was to determine the thresholds of lead concentration, stresses and potential in caustic and acidic sulfate solutions of the SCC-behaviour of Alloy 800 mod. and Alloy 690 TT. Therefore three types of examinations has been carried out in caustic solutions as well as in acidic sulfate solutions both contaminated with lead of different concentrations: to determine the influence of lead on the electrochemical behaviour current density-potential-curves has been done at 300 degree centigree. To determine the influence of potential as well as the influence of lead concentration exposure of C-rings under potentiostatic control were performed at 300 degree centigree. To determine the influence of stress and lead concentration exposure of C-rings in capsules at free corrosion potential were carried out at 315 degree centigree
Additional details
Publishing Information
- Publisher
- CIEMAT.
- Imprint Place
- Madrid (Spain)
- Imprint Title
- IAEA Specialist's meeting on steam generator problems and replacement
- Imprint Pagination
- 653 p.
- Journal Page Range
- p. 137-167.
Conference
- Title
- IAEA Specialists' meeting on steam generator problems and replacement.
- Dates
- 13-16 Dec 1993.
- Place
- Madrid (Spain).
INIS
- Country of Publication
- Spain
- Country of Input or Organization
- Spain
- INIS RN
- 25052535
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ELECTROCHEMICAL CORROSION; INCOLOY 800; INCONEL 690; LEAD; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; STEAM GENERATORS; STRESS CORROSION; TUBES
- Descriptors DEC
- ALLOY-FE46NI33CR21; ALLOY-NI59CR30FE9; ALLOYS; ALUMINIUM ADDITIONS; BOILERS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION; CORROSION RESISTANT ALLOYS; ELEMENTS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCOLOY ALLOYS; INCONEL ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; METALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; TITANIUM ADDITIONS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS