Transport processes in steam generator crevices. II. A simplified method for estimating impurity accumulation rates

Corrosion Science

Volumn 41, Issue 11, 1999, Pages 2191-2211

  Engelhardt, George R ^a   Macdonald, Digby D ^a   Millett, Peter J ^b  

^a SRI INTERNATIONAL   (United States)

^b ELECTRIC POWER RESEARCH INSTITUTE   (United States)

Author keywords

Boiling crevice model; Coupled environment fracture model; Steam generator corrosion

Indexed keywords

APPROXIMATION THEORY; FRACTURE; FUNCTION EVALUATION; MATHEMATICAL MODELS; PRESSURIZED WATER REACTORS; SUPERHEATER TUBES;

BOILING CREVICE MODEL;

BOILER CORROSION;

CORROSION; MATHEMATICAL MODELING; PRESSURIZED WATER REACTOR; STEAM GENERATING EQUIPMENT;

EID: 0033231355     PISSN: 0010938X     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0010-938X(99)00040-2     Document Type: Article

References (11)

1. Millett P.J., Fenton J.M. A detailed model of localized concentration processes in porous deposits of SG's. Environmental Degradation of Materials. Nuclear Power Systems-Water Reactors, Monterey, CA, August 25-29, 1991. 1991;NACE Publ.
2. P.J. Millett, Theoretical and Experimental Investigation in Local Concentration Processes in PWR Steam Generators. PhD Dissertation, University of Connecticut, 1991.
3. Wang R.C., Chin Pan, Chuen-Horn Tsai. Nucl. Tech. 94:1990;1.
4. Cleary J.G., VonNieda G.E., Lindsay W.T. Diffusion and Hideout in Crevices. EPRI NP2979, March. 1983.
5. Balakrishnan P.V. Concentration of chemicals within crevices in steam generators. Proceedings of Water Chemistry of Nuclear Reactor Systems 2, BNES, London, England, October. 1980.
6. Millett P.J., Fenton J.M. Transport processes in PWR support structure crevices. Proceedings of Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Jekyll Island, August. 1989.
7. Gonzalez F., Spekkens P. Nuclear Journal of Canada. 1:2:1988;129-240.
8. G. Engelhardt, D.D. Macdonald, P. Millett, Transport Processes in Steam Generator Crevices. I. General Corrosion Model, Corros. Sci (1998) (submitted).
9. Lumsden J.B., Pollok G.A., Stocker P.J., Millett P.J., Fauchon C. Hideout in prototypic tube/tube support plate heated crevices. Proceedings of the VIII International Symposium on Environmental Degradation of Materials in Nuclear Power Systems Water Reactor, Amelia Island, August. 1997.
10. Cohen P., The ASME Handbook on Water Technology for Thermal Power System. 1989;ASME.
11. Park J-R., Macdonald D.D. Corrosion. 45:1998;563.