4. Thermal Load of RPV

Precipitation in long term thermally aged high copper, high nickel model RPV steel welds

Crack growth behaviour of low-alloy steels for pressure boundary components under transient light water reactor operating conditions – CASTOC, Part 2: VVER conditions

Methods for the evaluation of crack resistance of reactor P.V. materials under conditions of thermal shock

Isothermal and thermal–mechanical fatigue of VVER-440 reactor pressure vessel steels

Short-term strength properties and features of high-temperature deformation of VVER reactor pressure vessel steel 15Kh2NMFA-A within the temperature range 20–1200 °C

Low cycle thermomechanical fatigue of reactor steels: Microstructural and fractographic investigations

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

Annealing behaviour of reactor pressure-vessel steels studied by positron-annihilation spectroscopy, Mössbauer spectroscopy and transmission electron microscopy

Mechanical properties and microstructure of long term thermal aged WWER 440 RPV steel

Effect of thermal aging on embrittlement of Cr–Mo–V pressure vessel steel

Recovery of the Transition Temperature of Irradiated WWER-440 Vessel Metal by Annealing

Back to Main menu