TEM characterization of in-reactor neutron irradiated CANDU spacer material Inconel X-750

摘要

The irradiation induced defects in CANDU Inconel X-750 spacers, which were removed from reactors after about 14 effective full power years, were examined by transmission electron microscopy (TEM). The spacers in the form of garter springs were reported to operate at various temperatures depending on locations. Two samples from different locations with different estimated irradiation temperatures were tested: (1) ~180℃ at 6 o'clock position and (2)≥300℃ at 12 o'clock position. Obvious temperature effects were observed. In the ~180℃ irradiated sample, a high density of small lattice defects(1-3 nm) developed during irradiation, including stacking fault tetrahedra and both 1/3 >111>and ? >110>type dislocation loops. A uniform distribution of small cavities (~1-3 nm) was observed. In >300℃ irradiated sample, apart from small point defect clusters, large Frank type interstitial loops presented. The sizes of the cavities were also greater than those in the ~180℃ irradiated sample. The distribution of cavities was more heterogeneous and an obvious agglomeration of cavities to grain boundaries and phase boundaries were observed. In both samples, dissolution of the primary strengthening phase γ was noted.