Effects of the feedwater sodium/chloride ratio and hydrazine on crevice chemistry

Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -

Volumn , Issue , 1999, Pages 545-553

  Lumsden, J B ^a   Pollock, G A ^a   Millett, P J ^b   Torigoe, N ^b   Takamatsu, H ^c  

^a ROCKWELL SCIENCE CENTER   (United States)

^b ELECTRIC POWER RESEARCH INSTITUTE   (United States)

^c KANSAI ELECTRIC POWER CO   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

ELECTROCHEMISTRY; POROSITY; PRESSURIZED WATER REACTORS; SODIUM CHLORIDE; STEAM GENERATORS;

CREVICE; SODIUM HYDROXIDE;

TUBES (COMPONENTS);

EID: 0033489255     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1002/9781118787618.ch57     Document Type: Conference Paper

References (7)

1. PWR Secondary Water Chemistry Guidelines Revision Committee, Interim Secondary Water Chemistry Recommendations for IGA/SCC Control, EPRI TR-101230, September 1992.
2. PWR Secondary Water Chemistry Guidelines Revision Committee, PWR Secondary Water Chemistry Guidelines-Revision 3, EPRI TR-102134, May 1993.
3. P.J. Millett, G.E. Brobst, and J. Riddle, "A Probabilistic Approach to Controlling Crevice Chemistry," Proceedings of the Seventh Symposium on the Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Breckenridge, CO, p. 663-674, NACE International, Houston Texas (1995).
4. J.B. Lumsden, G.A. Pollock, P.J. Millett, and C. Fauchon, "Hideout in Prototypic Tube/Tube Support Plate Heated Crevice," Proceedings of the Eighth Symposium on the Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Amelia Island, FA, p. 745-751, American Nuclear Society, La Grange Park, Illinois (1997).
5. G. M. W. Mann and R. Castle, "Hideout and Return of Chloride Salts in Heated Crevices Prototypic of Support Plates in Steam Generators", EPRI NP-5015, January 1987.
6. P.J. Millett, "A Detailed Model of Localized Concentration Processes in Porous Deposits of SG's," Proceedings of the Fifth Symposium on the Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Monterey, CA, p. 745-751, American Nuclear Society, La Grange Park, Illinois (1991).
7. J. R. Cels, "Stress Corrosion Cracking of Stainless Steel and Nickel Alloys at Controlled Potentials in 10% Caustic Soda Solutions at 550°F", J. Electrochem Soc. 123 (1976) 1152-1156.