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Radiation buildup and control in BWR recirculation piping

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7148320
Boiling water nuclear reactors (BWRs) employ stainless steel (Types 304 or 316 NG) pipes in which high-purity water at temperatures of approx. 275/sup 0/C are circulated. Various components of the system, such as valves and bearings, often contain hard facing metal alloys such as Stellite-6. These components, along with the stainless steel tubing and feedwater, serve as sources of /sup 59/Co. This cobalt, along with other soluble and insoluble impurities, is carried along with the circulating water to the reactor core where it is converted to radioactive /sup 60/Co. After reentering the circulating water, the /sup 60/Co can be incorporated into a complex corrosion layer in the form of CoCr/sub 2/O/sub 4/ and/or CoFe/sub 2/O/sub 4/. The presence of even small amounts of /sup 60/Co on the walls of BWR cooling systems is the dominant contributor to inplant radiation levels. Thus BWR owners and their agents are expending significant time and resources in efforts to reduce both the rate and amount of /sup 60/Co buildup. The object of this research is twofold: (a) to form a thin diffusion barrier against the outward migration of cobalt from a cobalt-containing surface and (b) to prevent the growth of a /sup 60/Co-containing corrosion film. The latter goal was the more important since most of the radioactive cobalt will originate from sources other than the stainless steel piping itself.
Research Organization:
Syracuse Univ., NY (USA)
OSTI ID:
7148320
Report Number(s):
CONF-8711195-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
Country of Publication:
United States
Language:
English