Radiation and annealing response of WWER 440 beltline welding seams


Radiation and annealing response of WWER 440 beltline welding seams

Viehrig, H.-W.; Houska, M.; Altstadt, E.

The focus of this paper is on the irradiation response and the effect of thermal annealing in weld materials extracted from decommissioned WWER 440 reactor pressure vessels of the nuclear power plant Greifswald. The characterisation is based on the measurement of the hardness, the yield stress, the Master Curve reference temperature, T0, and the Charpy-V transition temperature through the thickness of multi-layer beltline welding seams in the irradiated and the thermally annealed condition. Additionally, irradiation-induced defect/solute clusters were measured by small angle neutron scattering.
We observed a large variation in the through thickness T0 values in the irradiated as well as in thermally annealed condition. The T0 values measured with the T-S-oriented Charpy size SE(B) specimens cut from different thickness locations of the multilayer welding seams strongly depend on the intrinsic weld bead structure along the crack tip. The Master Curve, T0, and Charpy-V, TT47J, based ductile-to-brittle transition temperature progressions through the thickness of the multi-layer welding seam do not correspond to the forecast according to the Russian code.
Thermal annealing at 475°C for 152 h results in the expected decrease of the tensile strength and the shift of Master Curve and Charpy-V based ductile-to-brittle transition temperatures to lower temperatures.

Keywords: reactor pressure vessel; multi-layer welding seam; neutron irradiation; fracture toughness; Master Curve approach; Charpy-V

Permalink: https://www.hzdr.de/publications/Publ-20372