| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 10147638 | Journal of Nuclear Materials | 2018 | 17 Pages |
Abstract
In the framework of the SELENIUM project, ZrN coated U-Mo fuel kernels were irradiated in the Belgium Reactor 2 of SCK
- CEN to a plate average burnup of 48% 235U and a local maximum burnup just below 70% 235U. The microstructure and chemical composition of ZrN coating before and after neutron irradiation have been analysed using scanning transmission electron microscopy (STEM) equipped with energy dispersive X-ray spectroscopy (EDS) and electron energy loss spectroscopy (EELS), and atom probe tomography (APT). The atomic ratio of N/Zr and fission product distribution determined by three techniques were compared and the combination of three techniques shows the advantages in characterization of chemical information for nuclear materials.
- CEN to a plate average burnup of 48% 235U and a local maximum burnup just below 70% 235U. The microstructure and chemical composition of ZrN coating before and after neutron irradiation have been analysed using scanning transmission electron microscopy (STEM) equipped with energy dispersive X-ray spectroscopy (EDS) and electron energy loss spectroscopy (EELS), and atom probe tomography (APT). The atomic ratio of N/Zr and fission product distribution determined by three techniques were compared and the combination of three techniques shows the advantages in characterization of chemical information for nuclear materials.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
L. He, M. Bachhav, D.D. Keiser, J.W. Madden, E. Perez, B.D. Miller, J. Gan, W. Van Renterghem, A. Leenaers, S. Van den Berghe,