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Title: Development of ECP models for BWR applications

Book ·
OSTI ID:203748
;  [1];  [2];  [3]
  1. GE Corporate Research and Development Center, Schenectady, NY (United States)
  2. GE Vallecitos Nuclear Center, Pleasanton, CA (United States)
  3. Electric Power Research Inst., Palo Alto, CA (United States)

The electrochemical corrosion potential (ECP) of stainless steel has been measured under simulated Boiling Water Reactor (BWR) coolant circuit conditions using a rotating cylinder electrode. Based on the results of measurements an empirical model has been developed to predict the ECP of structure materials in a BVTR primary circuit as a function of H{sub 2}, O{sub 2}, and H{sub 2}O{sub 2} concentrations in reactor coolant and water flow velocity. The ECP modeling results using the H{sub 2}, O{sub 2}, and H{sub 2}O{sub 2} concentrations calculated by the radiolysis model are compared with the available reactor internal ECP data obtained in an operating reactor.

OSTI ID:
203748
Report Number(s):
CONF-950816-; ISBN 1-877914-95-9; TRN: 96:009714
Resource Relation:
Conference: 7. international symposium on environmental degradation of materials in nuclear power plants: water reactors, Breckenridge, CO (United States), 6-10 Aug 1995; Other Information: PBD: 1995; Related Information: Is Part Of Seventh international symposium on environmental degradation of materials in nuclear power systems -- Water reactors: Proceedings and symposium discussions. Volume 2; Airey, G.; Andresen, P.; Brown, J. [eds.] [and others]; PB: 620 p.
Country of Publication:
United States
Language:
English