About this Abstract |
Meeting |
MS&T24: Materials Science & Technology
|
Symposium
|
Ceramic Materials for Nuclear Energy Systems
|
Presentation Title |
Irradiation Study of TiN Inner-Wall Coating for Advanced Cladding to Suppress FCCI |
Author(s) |
Jian Gan, Yizhi Zhang, Yifan Zhang, Jiawei Song, Haiyan Wang, Yinbin Miao, Peter Mouche, Kun Mo, Bei Ye, Abdellatif M. Yacout, Brandon Miller, Laura Hawkins |
On-Site Speaker (Planned) |
Jian Gan |
Abstract Scope |
Advanced cladding is critical for the development of advanced nuclear reactors with enhanced performance in radiation tolerance and neutron transparency. It will ensure adequate thermal conductivity and mechanical stability of cladding base material, corrosion resistance and high temperature coolant compatibility of cladding surface. Finally, it provides chemical stability in the cladding inner-wall against fuel-cladding chemical interaction (FCCI). This presentation summarizes the recent ion irradiation studies of diffusion couple samples with details of an ion-irradiation experiment and transmission electron microscopy characterization of the interface microstructure of Ce/TiN/ODS, Ce/TiN/Fe, Ce/ODS and Ce/Fe samples irradiated with 80 MeV Xe ions to 100 dpa at 500 C using the ATLAS facility at Argonne National Laboratory. The preliminary results of ODS substrate sample are promising and demonstrate the effectiveness of a thin ceramic coating on FCCI mitigation. The results from Fe substrate sample reveal complex microstructure and need further investigation |