TY - CONF
T1 - Swift heavy ion irradiation of zirconium alloy
T2 - 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS/CNA Student Conference
AU - Kong, S.
AU - Bai, R.
AU - Hua, Z.
AU - Wang, W.
AU - Liu, L.
AU - Yuan, D.
AU - Ban, H.
AU - Xia, H.
N1 - Funding Information:
This work was financially supported by International Science and Technology Cooperation Project of China (2015DFA50510) .The authors would like to thank the staff of Shanghai Institute of Microsystem and Information Technology, Chinese Academy of Science for the TEM observation, the staff of Tsinghua University for the nano-indentation measurements and other colleagues in China Institute of Atomic Energy and State Power Investment Central Research Institute for their help in sample preparation and irradiation experiment.
PY - 2017
Y1 - 2017
N2 - 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°C and 700°C 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.
AB - 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°C and 700°C 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.
KW - Ion irradiation
KW - Nanoindentation
KW - Photothermal reflectance technique
KW - Zirconium alloy
UR - http://www.scopus.com/inward/record.url?scp=85040236347&partnerID=8YFLogxK
M3 - Paper
AN - SCOPUS:85040236347
Y2 - 4 June 2017 through 7 June 2017
ER -