German and Russian Irradiated Reactor Pressure Vessel Steels from PAS Point of View

• Authors: V. Slugeň , H. Hein , S. Sojak , S. Pecko , J. Šimeg Veterníková , M. Petriska , V. Sabelová , I. Bartošová , M. Stacho
• Languages of publication: EN

Abstracts

EN

This paper presents a comparison of commercially used German and Russian reactor pressure vessel steels from the positron annihilation spectroscopy point of view, having in mind knowledge obtained also from other techniques from the last decades. The second generation of Russian reactor pressure vessel steels seems to be fully comparable with German steels and their quality allows prolongation of NPP operating lifetime over projected 40 years. The embrittlement of CrMoV steels is very low due to the dynamic recovery of radiation-induced defects at reactor operating temperatures. Positron annihilation spectroscopy techniques can be effectively applied for evaluation of microstructural changes caused by extreme external loads by proton implantation, with aim to simulate irradiation and for the evaluation of the effectiveness of post-irradiation thermal treatments. We used our actual and previous results, collected during last 20 years from measurements of different reactor pressure vessel steels in "as received", irradiated and post-irradiation annealed state and compare them with the aim to contribute to general knowledge based on experimental positron annihilation spectroscopy data.

Keywords

EN

28.41.Qb; 61.72.-y; 78.70.Bj

Discipline

• 78.70.Bj: Positron annihilation(for positron states, see 71.60.+z in electronic structure of bulk materials; for positronium chemistry, see 82.30.Gg in physical chemistry and chemical physics)
• 61.72.-y: Defects and impurities in crystals; microstructure(for radiation induced defects, see 61.80.-x; for defects in surfaces, interfaces, and thin films, see 68.35.Dv and 68.55.Ln; see also 85.40.Ry Impurity doping, diffusion, and ion implantation technology; for effects of crystal defects and doping on superconducting transition temperature, see 74.62.Dh)
• 28.41.Qb: Structural and shielding materials

• Journal: Acta Physica Polonica A
• Year: 2014
• Volume: 125
• Issue: 3
• Pages: 726-728

Dates

published

2014-03

Contributors

author

V. Slugeň

• Institute of Nuclear and Physical Engineering, Slovak University of Technology Ilkovičova 3, 81219 Bratislava, Slovakia

author

H. Hein

• AREVA NP GmbH, Paul Gossen Str. 100, 91 001 Erlangen, Germany

author

S. Sojak

• Institute of Nuclear and Physical Engineering, Slovak University of Technology Ilkovičova 3, 81219 Bratislava, Slovakia

author

S. Pecko

• Institute of Nuclear and Physical Engineering, Slovak University of Technology Ilkovičova 3, 81219 Bratislava, Slovakia

author

J. Šimeg Veterníková

• Institute of Nuclear and Physical Engineering, Slovak University of Technology Ilkovičova 3, 81219 Bratislava, Slovakia

author

M. Petriska

• Institute of Nuclear and Physical Engineering, Slovak University of Technology Ilkovičova 3, 81219 Bratislava, Slovakia

author

V. Sabelová

• Institute of Nuclear and Physical Engineering, Slovak University of Technology Ilkovičova 3, 81219 Bratislava, Slovakia

author

I. Bartošová

• Institute of Nuclear and Physical Engineering, Slovak University of Technology Ilkovičova 3, 81219 Bratislava, Slovakia

author

M. Stacho

• Institute of Nuclear and Physical Engineering, Slovak University of Technology Ilkovičova 3, 81219 Bratislava, Slovakia

References

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Identifiers

DOI

10.12693/APhysPolA.125.726