Research Article

Specific Features of Structural-Phase State and Properties of Reactor Pressure Vessel Steel at Elevated Irradiation Temperature

Table 5

The summary results of mechanical tests and structural study of 15Kh2NMFAA steel specimens: as-received, after segregation provoking treatment, and after irradiation at 300°C and 400°C.

State, MPa, °СCarbides and carbonitrides, % of monolayer coverageη, %Precipitates Dislocation loops
Me7C3Me(C, N)(Cr, Mo)2Cρ, 1023 m−3, nmρ, 1021m−3, nm
, nmρ, 1019 m−3, nmρ, 1021 m−3, nmρ, 1020 m−3

As-received80–1008 ± 214-152.9 ± 0.535–452.5 ± 0.6000
Segregation provoking treatment3570–1507.2 ± 1.514-153.1 ± 0.540–502.3 ± 0.5143000
Irradiation at 300°С524680–1007 ± 213-143.5 ± 0.535–453.0 ± 0.2201.4 ± 0.22.5 ± 0.52.5 ± 0.85 ± 2
Irradiation at 400°C101780–1205.2 ± 1.08-96.8 ± 1.030–502.1 ± 0.56500

: the difference between the mean value of phosphorus concentration in the as-received and the current state, expressed in % of monolayer coverage. : the change in the yield strength; : the shift of the critical brittleness temperature; , ρ: the size and number density of different hardening structural elements.