TY - JOUR
T1 - Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C
AU - He, Lingfeng
AU - Harp, Jason M.
AU - Hoggan, Rita E.
AU - Wagner, Adrian R.
N1 - Publisher Copyright:
© 2017
PY - 2017/4/1
Y1 - 2017/4/1
N2 - Fuel swelling during normal reactor operations could lead to unfavorable chemical interactions when in contact with its cladding. As new fuel types are developed, it is crucial to understand the interaction behavior between fuel and its cladding. Diffusion experiments between U3Si2 and Zricaloy-4 (Zry-4) were conducted at 800 and 1000 °C up to 100 h. The microstructure of pristine U3Si2 and U3Si2/Zry-4 interdiffusion products were examined using scanning electron microscopy (SEM) and transmission electron microscopy (TEM) equipped with an energy dispersive X-ray spectroscopy (EDS) system. The primary interdiffusion product observed at 800 °C is ZrSi2, with secondary phases of U-Zr in the Zry-4, and Fe-Cr-W-Zr-Si phases at Zry-4/ZrSi2 interface and Fe-Cr-U-Si phases at ZrSi2/U-Si interface. The primary interdiffusion products at 1000 °C were Zr2Si, U-Zr-Fe-Ni, U, U-Zr, and a low melting point phase U6Fe.
AB - Fuel swelling during normal reactor operations could lead to unfavorable chemical interactions when in contact with its cladding. As new fuel types are developed, it is crucial to understand the interaction behavior between fuel and its cladding. Diffusion experiments between U3Si2 and Zricaloy-4 (Zry-4) were conducted at 800 and 1000 °C up to 100 h. The microstructure of pristine U3Si2 and U3Si2/Zry-4 interdiffusion products were examined using scanning electron microscopy (SEM) and transmission electron microscopy (TEM) equipped with an energy dispersive X-ray spectroscopy (EDS) system. The primary interdiffusion product observed at 800 °C is ZrSi2, with secondary phases of U-Zr in the Zry-4, and Fe-Cr-W-Zr-Si phases at Zry-4/ZrSi2 interface and Fe-Cr-U-Si phases at ZrSi2/U-Si interface. The primary interdiffusion products at 1000 °C were Zr2Si, U-Zr-Fe-Ni, U, U-Zr, and a low melting point phase U6Fe.
UR - http://www.scopus.com/inward/record.url?scp=85010822241&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2017.01.035
DO - 10.1016/j.jnucmat.2017.01.035
M3 - Article
AN - SCOPUS:85010822241
SN - 0022-3115
VL - 486
SP - 274
EP - 282
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
ER -