TY - JOUR
T1 - Nano-mechanical property assessment of a neutron-irradiated HT-9 steel cladding and a fuel-cladding chemical interaction region of a uranium–10 wt% zirconium nuclear fuel
AU - Thomas, Jonova
AU - Teng, Fei
AU - Murray, Daniel
AU - Okuniewski, Maria A.
N1 - Funding Information:
This work was supported by the US Department of Energy, Office of Nuclear Energy under DOE Idaho Operations Office Contract DE-AC07-051D14517 as part of a Nuclear Science User Facilities experiment. SEM and nano-indentation were carried out at the Irradiated Materials Characterization Laboratory at Idaho National Laboratory. This research was also partially supported by the US Nuclear Regulatory Commission through a Faculty Development Grant (M. A. Okuniewski) and fellowship (J. Thomas).
Publisher Copyright:
© 2021, The Author(s), under exclusive licence to The Materials Research Society.
PY - 2021/12/8
Y1 - 2021/12/8
N2 - Nano-indentation was used in conjunction with electron microscopy to characterize the microstructure and mechanical properties of a neutron-irradiated HT-9 cladding adjoined to uranium–10 wt% zirconium, a fast reactor fuel. Electron microscopy revealed that the neutron-irradiated cladding can be classified into three localities: HT-9 edge, HT-9 + fission products, and the fuel-cladding chemical interaction (FCCI) region. The three localities possessed differing nano-hardness values and consequently resulted in differing calculated yield stresses. Following irradiation, the nano-hardness and yield stresses increased in the HT-9 edge. The HT-9 + fission products locality also increased in nano-hardness and yield stresses with average values similar to the HT-9 edge, but with larger standard deviations due to the diffusion of fission products along grain boundaries. The FCCI locality had the largest and most variable nano-hardness and yield stresses in comparison to the other regions. A yield stress comparison of the HT-9 edge and the literature of neutron-irradiated HT-9 is discussed. Graphical abstract: [Figure not available: see fulltext.].
AB - Nano-indentation was used in conjunction with electron microscopy to characterize the microstructure and mechanical properties of a neutron-irradiated HT-9 cladding adjoined to uranium–10 wt% zirconium, a fast reactor fuel. Electron microscopy revealed that the neutron-irradiated cladding can be classified into three localities: HT-9 edge, HT-9 + fission products, and the fuel-cladding chemical interaction (FCCI) region. The three localities possessed differing nano-hardness values and consequently resulted in differing calculated yield stresses. Following irradiation, the nano-hardness and yield stresses increased in the HT-9 edge. The HT-9 + fission products locality also increased in nano-hardness and yield stresses with average values similar to the HT-9 edge, but with larger standard deviations due to the diffusion of fission products along grain boundaries. The FCCI locality had the largest and most variable nano-hardness and yield stresses in comparison to the other regions. A yield stress comparison of the HT-9 edge and the literature of neutron-irradiated HT-9 is discussed. Graphical abstract: [Figure not available: see fulltext.].
UR - http://www.scopus.com/inward/record.url?scp=85120789862&partnerID=8YFLogxK
UR - https://www.mendeley.com/catalogue/d3a33374-0637-377e-a362-769ab8252890/
U2 - 10.1557/s43580-021-00179-x
DO - 10.1557/s43580-021-00179-x
M3 - Article
AN - SCOPUS:85120789862
SN - 2059-8521
VL - 6
SP - 1048
EP - 1053
JO - MRS Advances
JF - MRS Advances
IS - 47-48
ER -