SYMPOSIA PAPER Published: 01 January 1994
STP23998S

Fatigue Crack Growth of Neutron Irradiated V-15Cr-5Ti and V-3Ti-1Si

Source

Compact-tension (CT) specimens of the alloys V-15Cr-5Ti and V-3Ti-1Si were irradiated to 3.8 × 1025n.m-2 (E > 0.1 MeV), corresponding to 4.0 dpa, at the temperatures 500, 600 and 700°C. Some specimens of the alloy V-3Ti-1Si were doped with 100 appm 10B, which during the irradiation was almost entirely transmuted to helium. Following irradiation constant-load-amplitude crack growth was measured at 200°C in air. All tests were performed at one R-ratio of 0.1 and a frequency of 2 Hz. Although both alloys in unirradiated condition showed similar crack growth rates as a function of the stress intensity factor range, the irradiated alloys behaved differently. The fatigue crack growth rate of V-3Ti-1Si irradiated at 500°C was slightly higher, with a lower dependence on the stress intensity factor range, compared to the unirradiated material, while after irradiation at 600 and 700°C the fatigue crack growth rate approached that of the unirradiated material. On the other hand, the alloy V-15Cr-5Ti irradiated at 500 and 600°C showed irregular crack growth and a higher growth rate, indicative of local unstable crack growth. After irradiation at 700°C the fatigue crack growth rate of this alloy also approached that of the unirradiated reference material. Limited data indicate that helium, generated by (n,α)-reaction with 10B, had no effect on the crack growth rate.

Author Information

Witzenburg, WV
Business Unit Nuclear Energy, Netherlands Energy Research Foundation, ECN, Westerduinweg 3, The Netherlands
de Bruyne, HJ
Business Unit Nuclear Energy, Netherlands Energy Research Foundation, ECN, Westerduinweg 3, The Netherlands
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Details
Developed by Committee: E10
Pages: 1201–1214
DOI: 10.1520/STP23998S
ISBN-EB: 978-0-8031-5262-5
ISBN-13: 978-0-8031-1488-3