Results 181 to 190 of about 3,105,065 (231)
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Microstructural evolution in reactor pressure vessel steels
Journal of Nuclear Materials, 1993Abstract The irradiation-induced changes occurring at the nanometer level in the microstructure of the reactor pressure vessel have been shown to be responsible for a degradation in mechanical properties that occur in large structures with dimensions in the tens of metres. These changes can place severe restrictions on the reactor both at the startup
W.J. Phythian, C.A. English
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Carbon analysis in reactor pressure vessel steels
Proceedings, annual meeting, Electron Microscopy Society of America, 1983The effect of neutron irradiation on the notch ductility transition temperature (NDTT) of A533B steel is known to be affected by the activity of the carbon atom which would be affected by its nearest neighboring substitutional atom, that is, silicon, manganese, etc.
O.C. de Hodgins +2 more
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NEUTRON EMBRITTLEMENT OF REACTOR PRESSURE VESSEL STEELS
1963This report presents the status of observations on the embrittlement of steels which are commonly used for the primary pressure containment vessels of nuclear power plants. The demonstrated criterion of nil ductility transition (NDT) temperature provides the basis for meaningful analysis of neutron-induced embrittlement in reactor steels.
J. R. Hawthorne, L. E. Steele
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Intergranular Embrittlement of Nuclear Reactor Pressure Vessel Steels
Key Engineering Materials, 2013Service 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
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Interactions of Defects with Dislocations in Reactor Pressure Vessel Steels
1993The 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.
R Schaller
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Radiation embrittlement of reactor pressure vessel steels
Nuclear Engineering and Design, 1966Abstract 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.
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Ratchetting behavior of 20MnMoNi55 reactor pressure vessel steel
Journal of Nuclear Materials, 2015Abstract 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
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Microstructural study of WWER reactor pressure vessel steels
Nuclear Engineering and Design, 2013Abstract 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
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Study of Lüders phenomena in reactor pressure vessel steels
Materials Science and Engineering: A, 2013We have undertaken a combined experimental and modelling study of plasticity development in samples containing notches and cracks in a reactor pressure vessel steel that exhibits the Lüders phenomenon in uniaxial testing. We have used digital image correlation to study the development of plasticity in plane sided, waisted and notched samples of a mild ...
Beardsmore, D. W. +7 more
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Strength problems of reactor steel pressure vessel of large dimensions
Nuclear Structural Engineering, 1965Abstract 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 ...
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