LYRA and other projects on RPV steel embrittlement

Debarberis, L.; Estorff, U. von; Crutzen, S.; Beers, M.; Stamm, H.; Vries, M.I. de; Tjoa, GL

doi:10.1016/s0029-5493(99)00244-7

Cited by 17 publications

(5 citation statements)

References 2 publications

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“…Properties of the RPV steels and influence of thermal and neutron treatment on these properties are routinely investigated by macroscopic methods such as Charpy V-notch and tensile tests [1,2,4,5,8]. A number of semi-empirical laws, based on macroscopic data, have been established, but, unfortunately, these laws are not completely consistent with all data and do not provide the desired accuracy.…”

Section: Introductionmentioning

confidence: 99%

Positron annihilation and Mössbauer spectroscopy applied to WWER-1000 RPV steels in the frame of IAEA High Ni Co-ordinated Research Programme

Slugeň

Zeman

Lipka

et al. 2004

NDT & E International

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Section: Introductionmentioning

confidence: 99%

Positron annihilation and Mössbauer spectroscopy applied to WWER-1000 RPV steels in the frame of IAEA High Ni Co-ordinated Research Programme

Slugeň

Zeman

Lipka

et al. 2004

NDT & E International

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“…The specimens were irradiated in the High Flux Reactor, at Petten (The Netherlands), in the LYRA irradiation rig, used in several projects organised by the Ageing Materials European Strategy (AMES) Network [4]. The irradiation was carried out at 270 8C, reaching an accumulated fluence of about 6.11 £ 10 22 N/m 2 (, 0.1 displacements per atom).…”

Section: Methodsmentioning

confidence: 99%

A preliminary evaluation of irradiation damage in model alloys by electric properties based techniques

Acosta

Filippo

Debarberis

2005

International Journal of Pressure Vessels and Piping

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“…There is no doubt that the degree of RPV embrittlement in a reactor pressure vessel (RPV) is a complex function of different parameters such as temperature, neutron fluence, flux, material chemistry, etc. [ 34 , 35 , 36 , 37 , 38 , 39 , 40 ].…”

Section: Introductionmentioning

confidence: 99%

Positron Annihilation Study of RPV Steels Radiation Loaded by Hydrogen Ion Implantation

et al. 2022

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Specimens of 15Kh2MFAA steel used for reactor pressure vessels V-213 (VVER-440 reactor) were studied by positron annihilation techniques in terms of their radiation resistance and structural recovery after thermal treatment. The radiation load was simulated by experimental implantation of 500keV H+ ions. The maximum radiation damage of 1 DPA was obtained across a region of 3 µm. Radiation-induced defects were investigated by coincidence Doppler broadening spectroscopy and positron lifetime spectroscopy using a conventional positron source as well as a slow positron beam. All techniques registered an accumulation of small open-volume defects (mostly mono- and di-vacancies) due to the irradiation, with an increase of the defect volume ΔVD ≈ 2.88 × 10−8 cm−3. Finally, the irradiated specimens were gradually annealed at temperatures from 200 to 550 °C and analyzed in detail. The best defect recovery was found at a temperature between 450 and 475 °C, but the final defect concentration of about ΔCD = 0.34 ppm was still higher than in the as-received specimens.

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LYRA and other projects on RPV steel embrittlement

Cited by 17 publications

References 2 publications

Positron annihilation and Mössbauer spectroscopy applied to WWER-1000 RPV steels in the frame of IAEA High Ni Co-ordinated Research Programme

Positron annihilation and Mössbauer spectroscopy applied to WWER-1000 RPV steels in the frame of IAEA High Ni Co-ordinated Research Programme

A preliminary evaluation of irradiation damage in model alloys by electric properties based techniques

Positron Annihilation Study of RPV Steels Radiation Loaded by Hydrogen Ion Implantation

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