Published December 1982
| Version v1
Report
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OTSG tube failures: upper tubesheet corrosion tests. Final report
Description
Several Alloy 600 tubes adjacent to the open lanes in the Oconee IB and IIB once-through steam generator failed near their juncture with the upper tubesheet. To help define the probable mechanism for these failures, a laboratory test program was undertaken. The test program indicated that the corrosion damage in the Oconee steam generators was probably caused by alkaline concentrates of sodium sulfate, silicate, and chloride. Actions taken to avoid this type of damage include reduction of contaminant levels in the steam generators feedwater and use of lane blockers to avoid transport of water droplets up the open lanes
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A05/MF A01 as DE83901118.
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The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 98 p.
- Report number
- EPRI-NP--2790
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14761964
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
- Descriptors DEI
- CORROSION; FAILURES; INCONEL 600; MICROSTRUCTURE; OCONEE-1 REACTOR; OCONEE-2 REACTOR; PERFORMANCE TESTING; REACTOR MATERIALS; STEAM GENERATORS; TUBES; WATER CHEMISTRY
- Descriptors DEC
- ALLOYS; BOILERS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CRYSTAL STRUCTURE; ENRICHED URANIUM REACTORS; INCONEL ALLOYS; IRON ALLOYS; MATERIALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIOBIUM ALLOYS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; TESTING; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WATER TREATMENT