TY - JOUR
T1 - Microstructural degradation of UN and UN-UO 2 composites in hydrothermal oxidation conditions
AU - Watkins, Jennifer K.
AU - Butt, Darryl P.
AU - Jaques, Brian J.
N1 - Publisher Copyright:
© 2019
PY - 2019/5
Y1 - 2019/5
N2 - The degradation behavior in high pressure water of UN and UN + (5–10 w%) UO 2 monolithic pellets fabricated from UN synthesized via a hydride-dehydride-nitride thermal process was investigated. Sintered pellets (>90% theoretical density) were subjected to hydrothermal oxidation in a water-filled static autoclave at temperatures ranging from 250 to 350 °C and pressures to 16.5 MPa. Phase characterization and microstructural and chemical analysis was performed on the resulting corrosion products using X-ray diffraction (XRD), scanning electron microscopy (SEM) coupled with energy dispersive spectroscopy (EDS). The results of this screening study show that grain boundary attack and spallation is the primary degradation mechanism in hydrothermal oxidation conditions. The results also suggest the corrosion rate is higher in UN and UN-UO 2 with higher starting oxygen content.
AB - The degradation behavior in high pressure water of UN and UN + (5–10 w%) UO 2 monolithic pellets fabricated from UN synthesized via a hydride-dehydride-nitride thermal process was investigated. Sintered pellets (>90% theoretical density) were subjected to hydrothermal oxidation in a water-filled static autoclave at temperatures ranging from 250 to 350 °C and pressures to 16.5 MPa. Phase characterization and microstructural and chemical analysis was performed on the resulting corrosion products using X-ray diffraction (XRD), scanning electron microscopy (SEM) coupled with energy dispersive spectroscopy (EDS). The results of this screening study show that grain boundary attack and spallation is the primary degradation mechanism in hydrothermal oxidation conditions. The results also suggest the corrosion rate is higher in UN and UN-UO 2 with higher starting oxygen content.
KW - Advanced technology fuel
KW - Hydrothermal degradation
KW - Nuclear fuel
KW - Uranium mononitride
UR - http://www.scopus.com/inward/record.url?scp=85062222324&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2019.02.027
DO - 10.1016/j.jnucmat.2019.02.027
M3 - Article
AN - SCOPUS:85062222324
SN - 0022-3115
VL - 518
SP - 30
EP - 40
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
ER -