TY - JOUR
T1 - Seeing through nuclear fuel
T2 - Three-dimensional, nondestructive X-ray microscopy and volumetric analyses of neutron-irradiated TRISO-coated fuel kernels
AU - Cordes, Nikolaus L.
AU - Chuirazzi, William C.
AU - Kane, Joshua J.
AU - Stempien, John D.
N1 - Funding Information:
This work was sponsored by the U.S. Department of Energy, Office of Nuclear Energy, through the Advanced Reactor Technologies Advanced Gas Reactor Fuel Development and Qualification Program. Idaho National Laboratory is operated by Battelle Energy Alliance LLC under contract number DE-AC07-05ID14517 for the U.S. Department of Energy.
Publisher Copyright:
© 2021, Battelle Energy Alliance, LLC (BEA), under exclusive licence to Materials Research Society.
PY - 2021/12
Y1 - 2021/12
N2 - The three-dimensional (3D) characterization of nuclear fuel with X-ray microscopy has historically proven difficult, due to uranium’s high attenuation of easily accessible X-rays, both in a laboratory setting and at a synchrotron user facility. However, this imaging modality provides nondestructive information that can be used to investigate morphological changes arising from external stimuli (e.g., neutron irradiation, high-temperature testing). Using an appropriate X-ray energy spectrum and an adequate X-ray filter, suitable transmissions through properly sized nuclear fuel specimens can be achieved. Here, we present the methods and results of using a commercially available, laboratory-based X-ray microscope (XRM) to examine the extent of 3D morphological changes of tristructural isotropic (TRISO)-coated fuel particles, specifically uranium oxide/uranium carbide fuel kernels, after high-temperature neutron irradiation. Graphical abstract: [Figure not available: see fulltext.]
AB - The three-dimensional (3D) characterization of nuclear fuel with X-ray microscopy has historically proven difficult, due to uranium’s high attenuation of easily accessible X-rays, both in a laboratory setting and at a synchrotron user facility. However, this imaging modality provides nondestructive information that can be used to investigate morphological changes arising from external stimuli (e.g., neutron irradiation, high-temperature testing). Using an appropriate X-ray energy spectrum and an adequate X-ray filter, suitable transmissions through properly sized nuclear fuel specimens can be achieved. Here, we present the methods and results of using a commercially available, laboratory-based X-ray microscope (XRM) to examine the extent of 3D morphological changes of tristructural isotropic (TRISO)-coated fuel particles, specifically uranium oxide/uranium carbide fuel kernels, after high-temperature neutron irradiation. Graphical abstract: [Figure not available: see fulltext.]
UR - https://www.scopus.com/pages/publications/85121371910
UR - https://www.mendeley.com/catalogue/4320058a-53da-3998-9515-14b8d3fecb9a/
U2 - 10.1557/s43580-021-00167-1
DO - 10.1557/s43580-021-00167-1
M3 - Article
AN - SCOPUS:85121371910
SN - 2059-8521
VL - 6
SP - 1043
EP - 1047
JO - MRS Advances
JF - MRS Advances
IS - 47-48
ER -