Conference Proceedings Paper
SWIFT HEAVY ION IRRADIATION OF ZIRCONIUM ALLOY: DELETERIOUS EFFECTS ON THERMAL AND MECHANICAL PROPERTIES
37th Annual CNS Conference - 2017 June 04-07
S. Kong (State Power Investment Central Research Institute (SPICRI))
R. Bai (China Institute of Atomic Energy, Beijing, China)
Z. Hua (Utah State University, Logan, USA)
W. Wang (SPICRI)
L. Liu (SPICRI)
D. Yuan (China Institute of Atomic Energy, Beijing, China)
H. Ban (Utah State University, Logan, USA)
H. Xia (SPICRI)
Zirconium alloy, used as cladding and structural material for reactor fuel assembly, will undergo harsh neutron irradiation environment. Swift heavy ion irradiation is one of the applicable methods to simulate typical neutron damage in Zr alloy. In present investigation, Zr alloy was irradiated at 300℃ and 700℃ by 80 MeV Ni9+ ions with two different doses of 4.35×1015 cm-2 and 8.7×1015 cm-2, which correspond to peak values of 5 dpa and 10 dpa. Three complementary analysis techniques, nanoindentation, laser-based photothermal reflectance thermal conductivity measurement technique and TEM were used to study irradiation damage before and after implantation. Results show that ion implantation enhances the alloy hardness and with the fluence increases and temperature decreases, hardness increases accordingly. The deduction of thermal diffusivity was also found after irradiation. These results are expected to deepen our understanding of Zr alloy and provide effective data for material optimization.
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