Influence of precipitate density on the nodular corrosion resistance of Zr-Sn-Fe-Cr alloys at 500 °C

Journal of Nuclear Materials

Volumn 288, Issue 2-3, 2001, Pages 237-240

  Charquet, D ^a  

^a Centre de Recherches d'Ugine 73403   (France)

Author keywords

[No Author keywords available]

Indexed keywords

ANNEALING; CORROSION RESISTANCE; PRECIPITATION (CHEMICAL); STEAM;

NODULAR CORROSION RESISTANCE;

ZIRCONIUM ALLOYS;

EID: 0035247350     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0022-3115(00)00728-5     Document Type: Article

References (10)

1. H.G. Weidinger, F. Garzarolli, C.M. Eucken, E.F. Baroch, in: Zirconium in the Nuclear Industry, ASTM-STP 939, 1987, p. 364.
2. F. Garzarolli, H. Stehle, in: Improvements in Water Reactor Fuel Technology and Utilization, IAEA, Vienna, 1987, p. 387.
3. T. Andersson, T. Thorvaldsson, in: Zirconium in the Nuclear Industry, ASTM-STP 939, 1987, p. 321.
4. B. Cheng, R.B. Adamson, in: Zirconium in the Nuclear Industry, ASTM-STP 939, 1987, p. 387.
5. P. Rudling, G. Wikmark, B. Lehtinen, H. Petterson, in: ASTM-STP 1354, 2000, p. 678.
6. B. Cheng, RM. Kruger, RM. Adamson, in: Zirconium in the Nuclear Industry, ASTM-STP 1245, 1994, p. 400.
7. Y. Etoh, K. Kikuchi, T. Yasuda, S. Koizumi, M. Oishi, Proceedings, International Topical Meeting on LWR Fuel Performance, Avignon, France ANS, ENS, 1991, p. 691.
8. D. Charquet, in: Zirconium in the Nuclear Industry, ASTM-STP 1354, 2000, p. 3.14.
9. D. Charquet, R. Tricot, J.F. Wadier, in: Zirconium in the Nuclear Industry, ASTM-STP 1023, 1989, p. 374.
10. D. Charquet, R. Hahn, E. Ortlieb, J.P. Gros, J.F. Wadier, in: Zirconium in the Nuclear Industry, ASTM-STP 1023, 1988, p. 405.