In-BWR and out-of-pile nodular corrosion behavior of Zry-2/4 type melts with varying Fe, Cr, and Ni content and varying process history

ASTM Special Technical Publication

Volumn 1295, Issue , 1996, Pages 865-883

  Ruhmann, H ^a   Manzel, R ^a   Sell, H J ^a   Charquet, D ^b  

^a SIEMENS AG   (Germany)

^b CEZUS   (France)

Author keywords

Annealing parameter; BWR cladding materials; In pile corrosion; Nodular corrosion; Zircaloy

Indexed keywords

ANNEALING; BOILING WATER REACTORS; CHROMIUM; COMPOSITION EFFECTS; CORROSION RESISTANCE; DOPING (ADDITIVES); INTERMETALLICS; IRON; NICKEL; PRECIPITATION (CHEMICAL); TRANSMISSION ELECTRON MICROSCOPY;

ANNEALING PARAMETERS; NODULAR CORROSION; ZIRCONIUM ALLOY ZIRCALOY;

ZIRCONIUM ALLOYS;

EID: 0030285575     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Review

References (9)

1. Steinberg, E., Weidinger, G., and Schaa, A. in Zirconium in the Nuclear Industry: Sixth International Symposium, ASTM STP 824, American Society for Testing and Materials, West Conshohocken, PA, 1984, pp. 106-122.
2. Garzarolli, F., Goll, W., Seibold, A., and Ray, I., "Effect of In-PWR Irradiation on Size, Structure, and Composition of Intermetallic Precipitates of Zr Alloys," this publication.
3. Charquet D. et al., "Solubility Limits and Formation of Intermetallic Precipitates in ZrSnFeCr Alloys," Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023, American Society for Testing and Materials, West Conshohocken, PA, 1988, pp. 405-422.
4. Maußner, G., Ortlieb, E., and Weidinger, H.-G., Basic Properties of Zirconium Alloys with Respect to Mechanical and Corrosion Behavior, BNES, London 1987, pp. 49-55.
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6. Bangaru, N. V., Busch, R. A., and Schemel, J. H., "Effect of Beta Quenching on the Micro Structure and Corrosion of Zircaloys," Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 939, American Society for Testing and Materials, West Conshohocken, PA, 1987, pp. 341-363.
7. Eucken, C. M., Finden, P. T., Trapp-Pritsching, S., and Weidinger, H.-G., "Influence of Chemical Composition on Uniform Corrosion of Zirconium-Based Alloys in Autoclave Tests," Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023, American Society for Testing and Materials, West Conshohocken, PA, pp. 113-127.
8. Weidinger, H.-G., Garzarolli, F., Eucken, C. M., and Baroch, E. F., "Effect of Chemistry on Elevated Temperature Nodular Corrosion," Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 939, American Society for Testing and Materials, West Conshohocken, PA, 1987, pp. 364-386.
9. Garzarolli, F., Steinberg, E., and Weidinger, H.-G., "Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy Cladding," Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023, American Society for Testing and Materials, West Conshohocken, PA, 1989, pp. 202-212.