Influence of transition elements Fe, Cr, and V on long-time corrosion in PWRs

ASTM Special Technical Publication

Volumn , Issue 1354, 2000, Pages 609-622

  Broy, Y ^a   Garzarolli, F ^a   Seibold, A ^a   Van Swam, L F ^b  

^a SIEMENS AG   (Germany)

^b SIEMENS CORPORATE RESEARCH   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CHROMIUM; COMPOSITION EFFECTS; CORROSION RESISTANCE; HYDROGEN EMBRITTLEMENT; IRON; NUCLEAR FUEL CLADDING; PRESSURIZED WATER REACTORS; VANADIUM;

ZIRCONIUM ALLOY ZIRCALOY;

ZIRCONIUM ALLOYS;

EID: 0033881333     PISSN: 10403094     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (9)

1. Kass, S., "The Development of the Zircaloys," Proceedings, USAEC Symposium on Zirconium Alloy Development, Castlewood, CA, 12-14 Nov. 1962, GEAP-4089.
2. Eucken, C. M., Finden, P. T., Trapp-Pritsching, S., and Weidinger, H. G., "Influence of Chemical Composition on Uniform Corrosion of Zirconium Base Alloys in Autoclave Tests," Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023, pp. 113-127.
3. Fuchs, H. P. et al., "Cladding and Structural Material Development for the Advanced Siemens PWR Fuel 'FOCUS'," Proceedings ANS-ENS International Topical Meeting on LWR Fuel Performance, Avignon, France, 1991, p. 682.
4. van Swam, L. F., Garzarolli, F., and Steinberg, E., "Advanced PWR Cladding," Proceedings, ANS International Topical Meeting on LWR Fuel Performance, West Palm Beach, FL, 1994, p. 303.
5. Seibold, A., Garzarolli, F., and Steinberg, E., "Optimized Zry-4 with Enhanced Fe and Cr Content and DUPLEX Cladding: The Answer to Corrosion in PWR," Proceedings, International KTG/ENS Topical Meeting on Nuclear Fuel, TOPFUEL 95, Würzburg, Germany, 12-15 March 1995, Vol. 2, p. 117.
6. Garzarolli, F., Broy, Y., and Busch, R. A., "Comparison of Long Time Corrosion of Certain Zr-Alloys in PWR, BWR and Laboratory Tests," Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, 1996, pp. 850-864.
7. Garzarolli, F., Stehle, H., Steinberg, E., and Weidinger, H. G., "Progress in the Knowledge of Nodular Corrosion," Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939, 1987, pp. 364-386.
8. Garzarolli, E. Goll, W., Seibold, A., and Ray, I., "Effect of PWR Irradiation on Size, Structure and Composition of Intermetallic Precipitates of Zr Alloys," Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, 1996, pp. 541-556.
9. Charquet, D. et al., "Hydrogen Absorption Kinetics During Zircaloy Oxidation in Steam," Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, 1994, pp. 80-97.