Corrosion performance of alternative steam generator materials and designs. Volume 2. Posttest examination of a seawater-faulted alternative materials model steam generator. Final report. [PWR]
Technical Report
·
OSTI ID:5282257
Corrosion results obtained from the post-test non-destructive and destructive examinations of an alternative materials model steam generator are described in this final report. The model operated under representative thermal and hydraulic and accelerated (high seawater contaminant concentration) steam generator secondary water chemistry conditions. Total exposure consisted of 114 steaming days under all volatile treatment (AVT) chemistry conditions followed by 282 fault steaming days at a 30 ppM chloride concentration in the secondary bulk water. Various support plate and lattice strip support designs incorporated Types 347, 405, 409 and SCR-3 stainless steels; Alloys 600 and 690; and carbon steel. Heat transfer tube materials included Alloy 600 in various heat treated conditions, Alloy 690, and Alloy 800. All tubing materials in this test exhibited moderate pitting, primarily in the sludge pile region above the tubesheet.
- Research Organization:
- Combustion Engineering, Inc., Windsor, CT (USA). Nuclear Power Systems
- OSTI ID:
- 5282257
- Report Number(s):
- EPRI-NP-3044-Vol.2; ON: DE84920065
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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CHEMICAL REACTIONS
CHEMISTRY
CHROMIUM ALLOYS
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CHROMIUM-NICKEL STEELS
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CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
HEAT RESISTANT MATERIALS
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INCONEL 600
INCONEL 690
INCONEL ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
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WATER MODERATED REACTORS