Published September 2001 | Version v1
Journal article

Investigation of neutron irradiated reactor vessel steels using post-irradiation annealing techniques

  • 1. Institute of Nuclear Safety System Inc., Mihama, Fukui (Japan)

Description

The matrix damage is known to be a major factor that contributes to embrittlement and hardening of irradiated reactor vessel steels, and is assumed to be composed of the point defect clusters. However field emission gun scanning transmission electron microscopy (FEGSTEM) and atom probe (AP) could not detect any evidence of the matrix damage. In this study, post irradiation annealing experiments combining positron annihilation lineshape analysis (PALA) and hardness experiments were applied to an actual surveillance test specimen and a sample of reactor vessel steel irradiated in a material test reactor (MTR), in order to investigate the matrix damage recovery behavior and its contribution to hardening. It was confirmed that higher fluence increased the hardness and the volume fraction of open volume defects and that higher flux decreased the thermal stability of matrix damage and the effect on hardening. The contribution of matrix damage to hardening could be estimated to be below 30%. (author)

Additional details

Publishing Information

Journal Title
INSS Journal
Journal Volume
8
Journal Page Range
p. 151-155
ISSN
1340-4482

Optional Information

Notes
6 refs., 3 figs., 4 tabs.