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Evaluation of the reactor pressure vessel steels by positron annihilation

Journal of Nuclear Materials, 2013
Abstract This paper presents a comparison of commercially used German and Russian reactor pressure vessel steels from the positron annihilation spectroscopy (PAS) point of view, having in mind knowledge obtained also from other techniques from the last decades.
V. Slugeň   +8 more
openaire   +1 more source

Intergranular Embrittlement of Nuclear Reactor Pressure Vessel Steels

Key Engineering Materials, 2013
Service life of VVER-type nuclear reactor is limited by decrease in brittle fracture resistance of reactor pressure vessel produced of low-alloy low-carbon steel under effect of irradiation and/or elevated temperatures. In this work fracture surfaces were studied by Auger-electron spectroscopy in order to estimate the contribution of intergranular ...
Oleg O. Zabusov   +5 more
openaire   +1 more source

Radiation embrittlement of reactor pressure vessel steels

Nuclear Engineering and Design, 1966
Abstract The problem of radiation embrittlement of reactor pressure vessel steels is considered within the framework of new NRL concepts of fracture analysis and in reference to the primary variables, steel composition, neutron exposure, and exposure temperature.
openaire   +1 more source

Positron Lifetime Study of Reactor Pressure Vessel Steels

physica status solidi (a), 2000
Positron lifetime (PL) study of several reactor pressure vessel (RPV) steels is presented. VVER-440 type Cr-Mo-V, VVER-1000 type Cr-Mo-Ni-V and A533-B RPV steels were included in the investigation. It was found that positrons annihilate from delocalized state or trapped at dislocations (lifetime 150 ps) in all specimens.
J. Čížek   +3 more
openaire   +1 more source

Strength problems of reactor steel pressure vessel of large dimensions

Nuclear Structural Engineering, 1965
Abstract The production of an operationally reliable pressure vessel for the reactor is one of the difficult tasks encountered in many projects of large nuclear power stations. These steel vessels have large dimensions (diameters from 3 m to 8 m) and a comparatively high internal pressure so that the basic wall thickness is sometimes amounting to ...
openaire   +1 more source

Microstructural study of WWER reactor pressure vessel steels

Nuclear Engineering and Design, 2013
Abstract This paper presents results from our long-term studies of irradiated, commercially used WWER reactor pressure vessel steels. Results from Charpy-V tests and positron annihilation spectroscopy techniques are compared and discussed in details, having in mind actual state of art and other microstructural studies in this area. The optimal region
V. Slugeň, A. Kryukov
openaire   +1 more source

Usnrc Research on Reactor Pressure Vessel Steel Embrittlement

1994
Meutron radiation embrittlement of nuclear reactor vessels continues to be a major concern of the USNRC. Research is sponsored for improving understanding of radiation embrittlement effects to predict margins of safety and to improve regulations. Regulatory issues that are affected by neutron embrittlement are examined and related to NRC research ...
A Taboada, M Mayfield
openaire   +1 more source

Ratchetting behavior of 20MnMoNi55 reactor pressure vessel steel

Journal of Nuclear Materials, 2015
Abstract Uniaxial ratchetting characteristics of 20MnMoNi55 steel at room temperature were studied experimentally. The effects of stress amplitude and mean stress on the ratchetting behavior of the steel were analyzed. It can be concluded that the ratchetting strain amplitude and ratchetting strain rate of 20MnMoNi55 steel increases with increasing ...
Apu Sarkar   +2 more
openaire   +1 more source

Interactions of Defects with Dislocations in Reactor Pressure Vessel Steels

1993
The radiation embrittlement of reactor pressure vessel steels may be partially explained by the creation of irradiation-induced defects that interact with the moving dislocations during plastic deformation. This research studies the nature of the interaction mechanisms and the microstructural properties and the mobility of the dislocations.
A Munier   +3 more
openaire   +1 more source

Analysis of Fracture Surfaces of Reactor Pressure-Vessel Steels

1982
The fracture surfaces of three A533-B pressure-vessel steels have been analyzed using Auger analysis scanning electron microscopy and X-ray microanalysis. The steels included both weld and plate materials with differing radiation sensitivity. The unirradiated specimens were fractured under different conditions to give both ductile and brittle failure ...
OC deHodgins, BL Shriver
openaire   +1 more source

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