An electrochemical monitoring facility was installed in the bypass of the “A" recirculation line in the Dresden-II boiling water reactor. Potentials of stainless steel and platinum were measured with a silver/silver chloride reference electrode from cold-standby to full-power operation. Simultaneous measurements of dissolved oxygen and reactor water conductivity were obtained. The potentials responded to the primary reactor water chemistry. At cold-standby, potentials of about 0.5 V vs the standard hydrogen electrode (SHE) were measured, which were indicative of neutral water that contained about 5 ppm dissolved oxygen and some hydrogen peroxide. The reactor startup resulted in a large drop in corrosion and oxidation potential due to the increase in temperature and change in water chemistry. Initial steady-state corrosion potentials approached −0.1 V (SHE) at about 525 F (274 C). No significant changes in potential were observed when normal flow or dead-leg conditions were maintained in the bypass line. These in-reactor potentials will be used to guide ex-reactor experiments to obtain a better understanding of specific corrosion phenomena.
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1 January 1978
Research Article|
January 01 1978
Monitoring Corrosion and Oxidation Potentials in a Boiling Water Reactor★ Available to Purchase
A. D. Miller
A. D. Miller
*General Electric Company, Boiling Water Reactor Systems Department, Pleasanton, California.
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Online ISSN: 1938-159X
Print ISSN: 0010-9312
© 1978 National Association of Corrosion Engineers
1978
CORROSION (1978) 34 (1): 3–6.
Citation
M. E. Indig, J. E. Weber, A. D. Miller; Monitoring Corrosion and Oxidation Potentials in a Boiling Water Reactor★. CORROSION 1 January 1978; 34 (1): 3–6. https://doi.org/10.5006/0010-9312-34.1.3
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