Results 171 to 180 of about 2,735 (205)
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Radiation Hardening and Embrittlement in a Reactor Pressure Vessel Steel
1969The relationship between the increase in tensile yield stress (YS) and the increase in the ductile-brittle transition temperature (DBTT) upon irradiation was studied for ASTM A 212-65 Grade B pressure vessel steel. Smooth tension specimens and Charpy V-notch impact specimens were irradiated in the same facility of the Oak Ridge Research Reactor under ...
M. S. Wechsler +3 more
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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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Steels for commercial nuclear power reactor pressure vessels
Nuclear Engineering and Design, 1969Abstract The properties of carbon and low alloy steels currently used in the USA for commercial nuclear power reactor pressure vessel construction are examined in reference to higher strength-higher alloy steels having potential for advanced reactor service.
R.H. Sterne, L.E. Steele
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Irradiation Tests of Several Steels for Reactor Pressure Vessels
1969The first trial irradiation tests of pressure vessel steels scheduled by the Steel Irradiation Joint Committee of Japan (SIJC) were begun in 1963 and completed in 1967. ASTM Specification A302 Grade B, modified A302B with nickel, HY-80, and several other domestic-made low-alloy high strength steels were selected.
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Modeling of Irradiation Embrittlement of Reactor Pressure Vessel Steels
Journal of Engineering Materials and Technology, 1999A model to describe the change in the inelastic and fracture properties of reactor pressure vessel steels due to neutron irradiation in the ductile region (i.e., irradiation embrittlement) is developed. First, constitutive equations for unirradiated elastic-viscoplastic-damaged materials are developed within the framework of the irreversible ...
S. Murakami, A. Miyazaki, M. Mizuno
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Validation of RTTo for German Reactor Pressure Vessel Steels
Volume 6: Materials and Fabrication, 2005For the introduction of the new reference temperature RTTo of the ASME Code Cases N-629 and N-631 into the German KTA rules the equation RTTo = T0 + 19,4 °C (35 °F) was validated by the re-evaluation of the existing fracture toughness data base of German RPV steels, including unirradiated and irradiated base material and weld metal data.
Elisabeth Keim +2 more
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Positron affinity for precipitates in reactor pressure vessel steels
Nuclear Engineering and Design, 1995The sensitivity of positron annihilation spectroscopy to irradiation-induced precipitates in reactor pressure vessel steels is discussed in the light of recent positron affinity and lifetime calculations. Carbide and nitride precipitates are found to trap positrons only if they contain metal vacancies.
Gerhard Brauer +3 more
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Acoustic emission measurements on reactor pressure vessel steel
Materials Science and Engineering, 1973Abstract Acoustic emission measurements have been made on laboratory specimens of reactor pressure vessel steel and the results correlated with crack tip yielding and crack extension. It has been shown that most of the emissions arise from plastic zone expansion, and that ductile crack growth is relatively quiet.
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Fracture of reactor pressure vessel steels
Materials Testing, 1975J. C. Radon, A. P. Glover, F. A. Johnson
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Microstructural Analysis of Nuclear Reactor Pressure Vessel Steels
1999One of the most fundamental tasks of nuclear-reactor safety research is assessing the integrity of the reactor’s pressure vessel (RPV). Properties of 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.
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