TY - JOUR
T1 - Development of radiation damage during in-situ Kr++ irradiation of Fe-Ni-Cr model austenitic steels
AU - Desormeaux, M.
AU - Rouxel, B.
AU - Motta, A. T.
AU - Kirk, M.
AU - Bisor, C.
AU - De Carlan, Y.
AU - Legris, A.
N1 - Funding Information:
The electron microscopy with in situ ion irradiation was accomplished at Argonne National Laboratory at the IVEM-Tandem Facility, a U.S. Department of Energy Facility funded by the DOE Office of Nuclear Energy , operated under Contract No. DE-AC02-06CH11357 by UChicago Argonne, LLC.
Publisher Copyright:
© 2016 Elsevier B.V. All rights reserved.
PY - 2016/7
Y1 - 2016/7
N2 - In situ irradiations of 15Cr/15Ni-Ti and 15Cr/25Ni-Ti model austenitic steels were performed at the Intermediate Voltage Electron Microscope (IVEM)-Tandem user Facility (Argonne National Laboratory) at 600 °C using 1 MeV Kr++. The experiment was designed in the framework of cladding development for the GEN IV Sodium Fast Reactors (SFR). It is an extension of previous high dose irradiations on those model alloys at JANNuS-Saclay facility in France, aimed at investigating swelling mechanisms and microstructure evolution of these alloys under irradiation [1]. These studies showed a strong influence of Ni in decreasing swelling. In situ irradiations were used to continuously follow the microstructure evolution during irradiation using both diffraction contrast imaging and recording of diffraction patterns. Defect analysis, including defect size, density and nature, was performed to characterize the evolving microstructure and the swelling. Comparison of 15Cr/15Ni-Ti and 15Cr/25Ni-Ti irradiated microstructure has lent insight into the effect of nickel content in the development of radiation damage caused by heavy ion irradiation. The results are quantified and discussed in this paper.
AB - In situ irradiations of 15Cr/15Ni-Ti and 15Cr/25Ni-Ti model austenitic steels were performed at the Intermediate Voltage Electron Microscope (IVEM)-Tandem user Facility (Argonne National Laboratory) at 600 °C using 1 MeV Kr++. The experiment was designed in the framework of cladding development for the GEN IV Sodium Fast Reactors (SFR). It is an extension of previous high dose irradiations on those model alloys at JANNuS-Saclay facility in France, aimed at investigating swelling mechanisms and microstructure evolution of these alloys under irradiation [1]. These studies showed a strong influence of Ni in decreasing swelling. In situ irradiations were used to continuously follow the microstructure evolution during irradiation using both diffraction contrast imaging and recording of diffraction patterns. Defect analysis, including defect size, density and nature, was performed to characterize the evolving microstructure and the swelling. Comparison of 15Cr/15Ni-Ti and 15Cr/25Ni-Ti irradiated microstructure has lent insight into the effect of nickel content in the development of radiation damage caused by heavy ion irradiation. The results are quantified and discussed in this paper.
UR - http://www.scopus.com/inward/record.url?scp=84963984691&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=84963984691&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2016.04.012
DO - 10.1016/j.jnucmat.2016.04.012
M3 - Article
AN - SCOPUS:84963984691
VL - 475
SP - 156
EP - 167
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
SN - 0022-3115
ER -