Evolution of weld metals nanostructure and properties under irradiation and recovery annealing of VVER-type reactors

Гурович, Б. А.; Кулешова, Е. А.; Shtrombakh, Ya. I.; Fedotova, Svetlana; Zabusov, O.; Prikhod’ko, K. E.; Zhurko, D. A.

doi:10.1016/j.jnucmat.2012.11.026

Cited by 37 publications

(18 citation statements)

References 16 publications

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“…TEM investigations were performed using a Titan-300 (FEI) transmission electron microscope in accordance with [16]. Research specimens were prepared from RPV steel blanks by bilateral electrochemical thinning using the Struers TenuPol-5 machine.…”

Section: Electron Microscopymentioning

confidence: 99%

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

Кулешова

Гурович

Krikun

et al. 2017

Science and Technology of Nuclear Installations

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This paper considers influence of elevated irradiation temperature on structure and properties of 15Kh2NMFAA reactor pressure vessel (RPV) steel. The steel is investigated after accelerated irradiation at 300 ∘ C (operating temperature of VVER-1000-type RPV) and 400∘ C supposed to be the operating temperature of advanced RPVs. Irradiation at 300 ∘ C leads to formation of radiationinduced precipitates and radiation defects-dislocation loops, while no carbide phase transformation is observed. Irradiation at a higher temperature (400 ∘ C) neither causes formation of radiation-induced precipitates nor provides formation of dislocation loops, but it does increase the number density of the main initial hardening phase-of the carbonitrides. Increase of phosphorus concentration in grain boundaries is more pronounced for irradiation at 400 ∘ C as compared to irradiation at 300 ∘ C due to influence of thermally enhanced diffusion at a higher temperature. The structural-phase changes determine the changes of mechanical properties: at both irradiation temperatures irradiation embrittlement is mainly due to the hardening mechanism with some contribution of the nonhardening one for irradiation at 400 ∘ C. Lack of formation of radiation-induced precipitates at = 400 ∘ C provides a small Δ shift (17 ∘ C). The obtained results demonstrate that the investigated 15Kh2NMFAA steel may be a promising material for advanced reactors with an elevated operating temperature.

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Section: Electron Microscopymentioning

confidence: 99%

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

Кулешова

Гурович

Krikun

et al. 2017

Science and Technology of Nuclear Installations

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show abstract

“…Therefore the selection of the annealing mode of the VVER-1000 RPV weld metal (WM) was based on the comprehensive studies of the features of the mechanisms that determine the degradation of their properties during operation. The differences in recovery annealing modes for VVER-440 and VVER-1000 RPV steels are due to the following [7][8][9][10][11]:…”

Section: Introductionmentioning

confidence: 99%

“…There is a significant contribution of grain boundary embrittlement (reversible temper embrittlement) to radiation embrittlement of VVER-1000 RPV WM in contrast to VVER-440 RPV WM wherein reversible temper embrittlement under irradiation does not appear [7][8][9]. For the necessary level of the phosphorus segregation annealing (dissolution) the temperatures of 550°C and above are required [11].…”

Section: Introductionmentioning

confidence: 99%

“…The regular mode of recovery annealing for these materials leads to a significantly incomplete return of the copper to the solid solution and, as a result, a slower rate of radiation embrittlement is observed under re-irradiation after recovery annealing [12,13]. Formation of Ni-rich precipitates under irradiation in VVER-1000 WM is not accompanied by any noticeable decrease of nickel content in matrix due to the significantly larger initial By combination of these factors the 565°C -100 h temperature-time mode with permissible temperature variation ±15°C (the basic mode) was chosen and justified for the VVER-1000 RPV WM [8][9][10]16].…”

Section: Introductionmentioning

confidence: 99%

“…The studies showed that regardless of the number of years the RPV had been under operation (regardless of fast neutron fluence at primary irradiation) the recovery annealing leads to the recovery of both microstructure and mechanical characteristics of welds [8].…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Evolution of microstructure and mechanical properties of VVER-1000 RPV steels under re-irradiation

Гурович

Кулешова

Shtrombakh

et al. 2015

Journal of Nuclear Materials

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Accelerating Irradiation-Induced Dislocation Loop Removal Using Electrical Pulses for Ultrafast Performance Regeneration

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et al. 2022

Metall Mater Trans A

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Evolution of weld metals nanostructure and properties under irradiation and recovery annealing of VVER-type reactors

Cited by 37 publications

References 16 publications

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

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

Evolution of microstructure and mechanical properties of VVER-1000 RPV steels under re-irradiation

Accelerating Irradiation-Induced Dislocation Loop Removal Using Electrical Pulses for Ultrafast Performance Regeneration

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