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CORROSION OF SILVER-INDIUM-CADMIUM IN BORATED HIGH TEMPERATURE WATER

Technical Report ·
OSTI ID:4019809
The corrosion behavior of bare Yankee Power Reactor control rod alloy (80 Ag-15 In-5 Cd) was evaluated in water corresponding to various simulated phases of reactor operation. The effect of chemical additives, such as boric acid as a soluble neutron poison and lithium hydroxide for pH adjustment, was considered. The bare alloy had previously been found to be undesirable for reactor use primarily due to the possibility of excessive release of corrosion products in the event of a high oxygen accident during operation. Suitably heat treated, electroplated nickel coatings were found to provide protection for the basic alloy in short term tests both with regard to gross attack and to internal oxidation. (auth)
Research Organization:
Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh
NSA Number:
NSA-15-025159
OSTI ID:
4019809
Report Number(s):
YAEC-147
Country of Publication:
United States
Language:
English