Results 151 to 160 of about 1,645 (179)

An Overview of Radiation Embrittlement Modeling for Reactor Vessel Steels

1993
The process by which reactor pressure vessel steels respond to neutron radiation exposure is very complex. Not only are the nuclear vessel materials varied in chemistry and processing history, but the embrittlement accumulation process is a function of many different variables, some of which we can only guess at their contributions.
WA Pavinich, TJ Griesbach, WL Server
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Physical and Mechanical Aspects of Radiation Embrittlement of RPV Steels

Volume 6: Materials and Fabrication, Parts A and B, 2008
A multi-scale approach to brittle fracture of irradiated RPV steels has been developed within the EURATOM FP6 Integrated Project PERFECT, and the EC-sponsored ISTC Project 3072: “Modelling of Brittle and Ductile Fracture and Prediction of Irradiation Damage Effects on Fracture Toughness Properties of Steels for Reactor Pressure Vessels on the Basis of ...
B. Margolin, V. Shvetsova, A. Gulenko, V. Nikolaev, D. Lidbury, E. Keim   +5 more
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Ultrasonic evaluation of radiation embrittlement in reactor vessel materials

AIP Conference Proceedings, 2001
Ultrasonic signal analysis from Charpy impact specimens have been performed in order to understand the ultrasonic characteristics of reactor vessel materials by neutron irradiation. The results showed that systematic changes in ultrasonic phase velocity versus neutron fluence were observed for the base metal, and inverse variations in the velocity ...
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The Relationship of Radiation Embrittlement and Swelling for Austenitic Steels for WWER Internals

Volume 6: Materials and Fabrication, Parts A and B, 2009
To investigate the effect of swelling upon mechanical properties of irradiated austenitic steel the investigations were conducted with steel 18Cr-10Ni-Ti and its weld irradiated up to same damage doses in two different temperature ranges: at the irradiation temperature of 330÷340°C when swelling is practically absent and at 400÷450°C when a ...
B. Z. Margolin, I. P. Kursevich, A. A. Sorokin, V. S. Neustroev   +3 more
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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
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The Influence of Impurity-Defect Interactions on Radiation Hardening and Embrittlement

Journal of Engineering Materials and Technology, 1979
It has been established that copper and other trace elements have a detrimental effect on the notch-impact properties of ferritic pressure vessel steels irradiated at reactor operating temperatures of about 288°C (550°F). The underlying cause, however, of this trace element effect has not been established. But based on radiation damage work on vanadium
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Influence of boron on radiation embrittlement of low-alloy steel

Soviet Atomic Energy, 1976
V. A. Nikolaev, V. I. Badanin
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Radiation Embrittlement of Reactor Pressure Vessel Steels

2003
C.A. English, J.M. Hyde
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Determination of Copper in A533b Steel for the Assessment of Radiation Embrittlement Using Laser-Induced Breakdown Spectroscopy

Applied Spectroscopy, 1996
Wolfgang E Ernst
exaly  

PAS assessment of radiation embrittlement of RPV welds

AIP Conference Proceedings
Sofia Gašparová, Vladimír Kršjak, Matúš Húska, Vladimír Slugeň, Stanislav Sojak, Martin Petriska, Yamin Song, Jarmila Degmová   +7 more
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