Investigation on Fatigue Behavior of Zircaloy -4 Alloy in Room Temperature and 380°C Condition

Abstract:

Zr-4 alloy is the material of nuclear fuel shell in nuclear power plant’s PWR. This paper presents this material’s general mechanical property and fatigue behavior that are tested in accordance with ASTM in room temperature and 380°C condition. The test results show that there is no cyclic hardening or cyclic softening phenomena for Zr-4 alloy applied by cyclic loading in room temperature condition. The fatigue design curve is obtained by processing fatigue test results with adopting ASME Sec.Ⅲ based on the test results of strain fatigue property. The research result shows the fatigue design data at different temperature may be corrected by elastic modulus with room temperature curve. This paper’s result may be used in PWR component design.

• Periodical: Key Engineering Materials (Volumes 297-300)
• Pages: 1005-1012
• DOI: https://doi.org/10.4028/www.scientific.net/KEM.297-300.1005
• Online since: November 2005
• Authors: Wei Ming Sun, Kangda Zhang, Xing Ren
• Keywords: Fatigue Behaviour, Material Property, Zircaloy-4

References

[1] W.J. O'Donnell & B.F. Langer: Fatigue Design for Zircaloy Components Nuclear Science and Engineering 20, 1-12 (1964).

[2] ASME Boiler and pressure Vessel Code Section Ⅲ (2001).

[3] Brun. G.: Cumulative Fatigue and Creep -Fatigue Damage at 350℃on Recrystallized Zircaloy-4 ASTM STP939 (1987), pp.597-616.

DOI: 10.1520/stp28146s

[4] C.E. Jaske & W.J. O'Donnell: Fatigue Design for Pressure Vessel Alloys, Journal of Pressure Vessel Technology, (Nov. 1977), pp.584-592.

DOI: 10.1115/1.3454577