Results 161 to 170 of about 308 (200)

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, Bhupendra K. Kumawat, J.K. Chakravartty   +2 more
openaire   +1 more source

The fatigue behavior of irradiated Reactor Pressure Vessel steel

Engineering Failure Analysis, 2017
Abstract Fatigue specimens of A508-3 steel were irradiated in the swimming-pool test reactor in China Institute of Atomic Energy, the fluence was 3 × 10 19  n/cm 2 at 300 °C, then low-cycle fatigue tests were carried out at ambient temperature, with the fatigue strain range is 0.32–1.8%. The results indicate that, irradiated A508-3 specimens exhibit
W. Zhong, Z. Tong, G. Ning, C. Zhang, H. Lin, W. Yang   +5 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

Radiation Hardening and Embrittlement in a Reactor Pressure Vessel Steel

1969
The 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, R. G. Berggreen, N. E. Hinkle, W. J. Stelzman   +3 more
openaire   +1 more source

Study of Lüders phenomena in reactor pressure vessel steels

Materials Science and Engineering: A, 2013
We 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., da Fonseca, J. Quinta; id_orcid 0000-0001-6063-8135, Romero, J., English, C. A., Ortner, S. R., Sharples, J., Sherry, A. H.; id_orcid 0000-0002-7413-4787, Wilkes, M. A.   +7 more
openaire   +2 more sources

Steels for commercial nuclear power reactor pressure vessels

Nuclear Engineering and Design, 1969
Abstract 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
openaire   +1 more source

Irradiation Tests of Several Steels for Reactor Pressure Vessels

1969
The 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.
openaire   +1 more source

Modeling of Irradiation Embrittlement of Reactor Pressure Vessel Steels

Journal of Engineering Materials and Technology, 1999
A 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
openaire   +1 more source

Validation of RTTo for German Reactor Pressure Vessel Steels

Volume 6: Materials and Fabrication, 2005
For 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, Dieter Siegele, Gerhard Nagel   +2 more
openaire   +1 more source

Positron affinity for precipitates in reactor pressure vessel steels

Nuclear Engineering and Design, 1995
The 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, Martti J Puska, Mojmir Sob, Timo Korhonen   +3 more
openaire   +1 more source