Corrosion Issues in Light Water Reactors: Stress Corrosion by D Fron

By D Fron

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Additional info for Corrosion Issues in Light Water Reactors: Stress Corrosion Cracking (EFC51)

Example text

The corrosion potential (often called ECP) was found to be the prime parameter controlling IGSCC. Hydrogen water chemistry (HWC) was developed and introduced as a remedy. Electrochemical measurements were introduced during so-called HWC mini-tests, which were performed to determine the necessary injection rate of hydrogen to reduce the corrosion potential below the critical potential for IGSCC. ECP monitoring equipment was first installed in remote sampling systems and the desired response to hydrogen was easily obtained.

Staehle, J. A. Gorman, K. D. Stavropoulos, C. S. Welty, ‘Application of statistical distributions to characterizing and predicting corrosion of tubing in steam generators of Pressurized Water Reactors’, Proceedings of Life Prediction of Corrodible Structures, ed. R. N. Parkins, NACE International (1994) 1374–1439. 8. P. Scott, C. Benhamou, ‘An overview of recent observations and interpretation of IGSCC in nickel base alloys in PWR primary water’, Proceedings of 10th Int. Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Lake Tahoe, NACE International (2001).

P. M. Scott, M-C. Meunier, D. Deydier, S. Silvestre, A. Trenty, ‘An analysis of baffle/former bolt cracking in French PWRs’, ASTM STP 1401 Environmentally Assisted Cracking: Predictive methods for Risk Assessment and Evaluation of Materials, Equipment and Structures, Ed. R. D. Kane, ASTM (2000) 210–223. S. M. Bruemmer, E. P. Simonen, P. M. Scott, P. L. Andresen, G. S. Was, J. L. Nelson, ‘Radiation-induced material changes and susceptibility to Intergranular failure of light-water-reactor core internals’, Journal of Nuclear Materials, 274 (1999) 299– 314.

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