Radiation Swelling of Materials Pressure Vessel Internals of WWER Reactors

Scientific Report at NAS of Ukraine Presidium Meeting 2 October 2013

Abstract

The systematic data on swelling of 0₈Cr₁₈Ni₁₀Ti steel — material of pressure vessel internals of WWER reactors — under different irradiation parameters (dose, temperature, dose rate, concentration of hydrogen and helium) are obtained by the method of simulation by accelerator. The features in the effect of helium and hydrogen on the processes of swelling versus irradiation temperature variation are established. A function which describes the swelling of the investigated steel in a wide range of doses, temperatures and dose rates is plotted both for reactor conditions as for irradiations in ion accelerators. Prediction of 0₈Cr₁₈Ni₁₀Ti steel swelling behaviour over a cross-section of the baffle ring of a WWER-1000 reactor during long-term operation 30—60 years is made. Swelling of oxide dispersion strengthened (ODS) 0₈Cr₁₈Ni₁₀Ti promising steel was investigated after the irradiation in accelerator. It was determined that swelling resistance of ODS 0₈Cr₁₈Ni₁₀Ti steel is higher than that of 0₈Cr₁₈Ni₁₀Ti steel.