Recently, annealed specimens of pure copper have been tensile tested in a fission reactor at a damage rate of 6 × 10−8 dpa/s with a constant strain rate of 1.3 × 10−7 s−1. The specimen temperature during the test was about 90 °C. The stress response was continuously recorded as a function of irradiation time (i.e. displacement dose and strain). The experiment lasted for 308 h. During the dynamic in-reactor test, the specimen deformed and hardened homogeneously without showing any sign of yield drop and plastic instability. However, the specimen yielded a uniform elongation of only about 12%. The preliminary results are briefly described and discussed in the present note.
- irradiation damage
- irradiation embrittlement
- neutron irradiation
Singh, B. N., Tähtinen, S., Moilanen, P., Jacquet, P., & Dekeyser, J. (2003). In-reactor uniaxial tensile testing of pure copper at a constant strain rate at 90 ºC. Journal of Nuclear Materials, 320(3), 299-304. https://doi.org/10.1016/S0022-3115(03)00234-4