Effect of neutron irradiation on tensile properties of advanced Cu-based alloys and composites developed for fusion applications

• Published in: Journal of nuclear materials 2023-10, Vol.584, p.154587, Article 154587
• Main Authors: Terentyev, Dmitry, Rieth, Michael, Pintsuk, Gerald, Von Müller, Alexander, Antusch, Steffen, Zinovev, Aleksandr, Bakaev, Alexander, Poleshchuk, Kateryna, Aiello, Giacomo
• Format: Article
• Language: English
• Subjects: Alloys; Composites; Copper; Irradiation
• ISSN: 0022-3115
• DOI: 10.1016/j.jnucmat.2023.154587

•Neutron irradiation embrittles W-CuCrZr laminates.•Fiber reinforced CuCrZr sustains ductility and high strength after neutron irradiation.•Vanadium-doped and ODS alloyed materials soften under 450 °C irradiation. The effect of neutron irradiation on tensile properties and fracture mode has been investigated for several advanced CuCrZr alloys in the frame of the European fusion material development program. Five material grades utilizing different strengthening principles have been exposed to neutron irradiation up to ∼2.5 dpa (displacement per atom) in the target operational temperature range of 150–450 °C. The strengthening mechanisms are based on the application of: i) tungsten particles; ii) tungsten foils (laminate structure); iii) tungsten fibers; iv) Y2O3 particles; v) vanadium addition (0.22%). Neutron irradiation was performed in the BR2 material test reactor inside the fuel channel in order to maximize the fast neutron flux. The upper irradiation temperature of 450 °C was selected to validate the ability of the pre-selected advanced grades to sustain the high temperature irradiation, since the baseline ITER specification CuCrZr is known not to retain sufficient tensile strength above 400 °C in non-irradiated conditions and shows strong irradiation induced softening above 300 °C. Neutron irradiation at 150 °C caused severe embrittlement of tungsten-copper laminates as well as a considerable reduction of the total elongation of all other grades. The irradiation at 450 °C led to the reduction of the yield strength and ultimate tensile strength (i.e. irradiation softening) in the vanadium-doped alloy similar to CuCrZr, while all other materials preserved or increased their strength (irradiation hardening). The fracture surfaces of the tested samples were analysed to investigate the modification of the deformation mechanisms in each particular case. Synthesis of the results indicating the effect of the irradiation on the studied materials. In the relevant figures, the irradiation temperature is equal to the test temperature. (a) UTS for the irradiated (upper pane) and (b) non-irradiated samples (lower pane). For the baseline ITER-specification CuCrZr in two heat treatments (SAcwA and SAA) minimum tensile strengths are provided in the temperature range of 150–350 °C as collected in [6]. (c) change of the tensile strengths (upper pane) and (d) absolute value of the uniform elongation (lower pane). [Display omitted]