DELISA-LTO

5. Radiation Load of RPV

Mechanical behavior of high-Ni/high-Mn Barsebäck 2 reactor pressure vessel welds after 28 years of operation

Investigation of high temperature annealing effectiveness for recovery of radiation-induced structural changes and properties of 18Cr–10Ni–Ti austenitic stainless steels

Development of the AMES network throughout the 4th and 5th EURATOM framework programmes

Annealing and re-embrittlement of reactor pressure vessel materials

Radiation Damage of Reactor Pressure Vessel Steels Studied by Positron Annihilation Spectroscopy—A Review

Microstructure alterations in the base material, heat affected zone and weld metal of a 440-VVER-reactor pressure vessel caused by high fluence irradiation during long term operation; material: 15 Ch2MFA ≈0.15 C–2.5 Cr–0.7 Mo–0.3 V

Embrittlement of low copper VVER 440 surveillance samples neutron-irradiated to high fluences

Radiation damage study using small-angle neutron scattering

Examination of VVER-440 RPV steel re-irradiation behavior using materials from operating units

Irradiation effects on toughness behaviour and microstructure of VVER-type pressure vessel steels

Atom probe tomography of 15Kh2MFA Cr–Mo–V steel surveillance specimens

Comparative small-angle neutron scattering study of neutron-irradiated Fe, Fe-based alloys and a pressure vessel steel

Transmission electron microscopy study on neutron irradiated pure iron and RPV model alloys

Precipitation kinetics of radiation-induced Ni-Mn-Si phases in VVER-1000 reactor pressure vessel steels under low and high flux irradiation

Predictive reactor pressure vessel steel irradiation embrittlement models: Issues and opportunities

Characterization of neutron-irradiated ferritic model alloys and a RPV steel from combined APT, SANS, TEM and PAS analyses

Formation and evolution of MnNi clusters in neutron irradiated dilute Fe alloys modelled by a first principle-based AKMC method

Nanostructure evolution under irradiation of Fe(C)MnNi model alloys for reactor pressure vessel steels

Assessment of segregation kinetics in water-moderated reactors pressure vessel steels under long-term operation

Effect of Ni content on thermal and radiation resistance of VVER RPV steel

Small angle scattering study concerning the effect of residual elements on the radiation behaviour of iron alloys

Master Curve and Unified Curve applicability to highly neutron irradiated Western type reactor pressure vessel steels

Behavior of mechanical properties of nickel-alloyed reactor pressure vessel steel under neutron irradiation and post-irradiation annealing

TEM and PAS study of neutron irradiated VVER-type RPV steels

Microstructural evolution of RPV steels under proton and ion irradiation studied by positron annihilation spectroscopy

Effects of neutron flux on irradiation-induced hardening and defects in RPV steels studied by positron annihilation spectroscopy

Evaluation of the reactor pressure vessel steels by positron annihilation

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

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