Corrosion behavior of duplex and reference cladding in NPP grohnde

ASTM Special Technical Publication

Volumn 1295, Issue , 1996, Pages 805-824

  Besch, Otto A ^a   Yagnik, Suresh K ^b   Woods, Keith N ^c   Eucken, Craig M ^d   Bradley, E Ross ^e  

^a EON Kernkraft GmbH   (Germany)

^b ELECTRIC POWER RESEARCH INSTITUTE   (United States)

^c SIEMENS CORPORATE RESEARCH   (United States)

^d Teledyne Wan Chang   (United States)

^e Sandvik Special Metals Corp   (United States)

Author keywords

Alloy development; Autoclave; Corrosion; Fuel cladding; Hydrides; In reactor performance; Microstructure; Nuclear applications; Radiation effects; Steam; Water; Zirconium alloys

Indexed keywords

CORROSION RESISTANCE; HYDRIDES; NUCLEAR FUEL CLADDING; PRESSURIZED WATER REACTORS;

ALLOY DEVELOPMENT;

ZIRCONIUM ALLOYS;

EID: 0030286664     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp16202s     Document Type: Article

References (3)

1. Perovic, A., Pervoic, V., Weatherly, G. C., Purdy, G. R., and Fleck, R. G., "A Study of the Distribution of Nb and Fe in Two-Phase Zr-2.5 wt% Nb Alloys," Journal of Nuclear Materials, Vol. 199, 1993, pp. 102-111.
2. Miyake, C. and Gotoh, K., "Magnetic Study of Zircaloy, II Zircaloy with Additive of Niobium," Journal of Nuclear Materials, Vol. 184, 1991, pp. 212-220.
3. Sabol, G. P., Comstock, R. J., Weiner, R. A., Larouere, P., and Staunz, R. N., "In-Reactor Corrosion Performance of ZIRLO and Zircaloy-4," Zirconium in the Nuclear industry: Tenth International Symposium, ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., American Society of Testing and Materials, West Conshohocken, PA, 1994, pp. 724-744.