Positron annihilation study of Fe-ion irradiated reactor pressure vessel model alloys

Journal Article (2016)
Author(s)

L. Chen (Tsinghua University, University of Tokyo)

Z. C. Li (Tsinghua University)

H. Schut (TU Delft - RST/Neutron and Positron Methods in Materials)

N. Sekimura (University of Tokyo)

Research Group
RST/Neutron and Positron Methods in Materials
Copyright
© 2016 L. Chen, Z. C. Li, H. Schut, N. Sekimura
DOI related publication
https://doi.org/10.1088/1742-6596/674/1/012012
More Info
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Publication Year
2016
Language
English
Copyright
© 2016 L. Chen, Z. C. Li, H. Schut, N. Sekimura
Research Group
RST/Neutron and Positron Methods in Materials
Issue number
1
Volume number
674
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Abstract

The degradation of reactor pressure vessel steels under irradiation, which results from the hardening and embrittlement caused by a high number density of nanometer scale damage, is of increasingly crucial concern for safe nuclear power plant operation and possible reactor lifetime prolongation. In this paper, the radiation damage in model alloys with increasing chemical complexity (Fe, Fe-Cu, Fe-Cu-Si, Fe-Cu-Ni and Fe-Cu-Ni-Mn) has been studied by Positron Annihilation Doppler Broadening spectroscopy after 1.5 MeV Fe-ion implantation at room temperature or high temperature (290 oC). It is found that the room temperature irradiation generally leads to the formation of vacancy-type defects in the Fe matrix. The high temperature irradiation exhibits an additional annealing effect for the radiation damage. Besides the Cu-rich clusters observed by the positron probe, the results show formation of vacancy-Mn complexes for implantation at low temperatures.

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