Radiation and annealing response of WWER 440 beltline welding seams
Description
Highlights: • Investigation of the beltline welding seam from decommissioned reactor pressure vessels. • The Master Curve based reference temperature varies strongly through the thickness. • This variation is mainly caused by the intrinsic weld bead structure. • The Charpy-V based ductile-to-brittle temperature shift does not correspond to the prediction. • The mitigation of the irradiation induced embrittlement by annealing has been confirmed. - Abstract: 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, the weld bead structure was characterised by light microscopic studies. 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. In general, the fracture toughness values at cleavage failure, KJc, measured on SE(B) specimens from the irradiated and large-scale thermally annealed beltline welding seams follow the Master Curve description, but more than the expected number lie outside the curves for 2% and 98% fracture probability. In this case the test standard ASTM E1921 indicates the investigated multi-layer weld metal as not uniform. The multi modal Master Curve based approach describes the temperature dependence of the specimen size adjusted KJc-1T values well. Thermal annealing at 475 °C for 152 h results in the expected decrease of the hardness and tensile strength and the shift of Master Curve and Charpy-V based ductile-to-brittle transition temperatures to lower values
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2014.10.004Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2014.10.004;
- PII
- S0022-3115(14)00687-4;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 456
- Journal Page Range
- p. 334-343
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46113190
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- ANNEALING; CLEAVAGE; CURRENT DENSITY; DUCTILE-BRITTLE TRANSITIONS; FRACTURE PROPERTIES; FRACTURES; HARDNESS; IRRADIATION; NUCLEAR POWER PLANTS; STRESSES; TENSILE PROPERTIES; THICKNESS; TRANSITION TEMPERATURE; WELDING; WWER TYPE REACTORS
- Descriptors DEC
- DIMENSIONS; ENRICHED URANIUM REACTORS; FABRICATION; FAILURES; HEAT TREATMENTS; JOINING; MECHANICAL PROPERTIES; MICROSTRUCTURE; NUCLEAR FACILITIES; PHYSICAL PROPERTIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.