Results 151 to 160 of about 341 (167)
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Investigation of an Updated Continuum Damage Model in the DBTT Region

AIP Conference Proceedings, 2010
With the investigation of influence of the stress triaxiality on the fracture properties, an updated continuum damage model is proposed and realized by FEA to evaluate the temperature effect and the strain rate effect on the fracture properties in the ductile and brittle transition temperature (DBTT) region.
Zhao-Xi Wang   +8 more
openaire   +1 more source

EFFECT OF THE PRECIPITATION OF Cu-RICH CLUSTERS ON THE DBTT OF RPV SIMULATED STEEL

Acta Metallurgica Sinica, 2012
Reactor pressure vessels(RPVs) are usually made of low alloy ferritic steels,among which A508-Ⅲsteel is a typical one.The long-term neutron irradiation can induce the embrittlement of RPV steels,and the embrittlement may lead to a reduction of the RPV service life.Generally, this behavior of the embrittlement is well established and is typically ...
Gang XU   +5 more
openaire   +1 more source

An updated continuum damage model to investigate fracture process of structures in DBTT region

International Journal of Fracture, 2008
zbMATH Open Web Interface contents unavailable due to conflicting licenses.
Wang, Zhao-Xi   +4 more
openaire   +2 more sources

Determination of Ductile-Brittle Transition Temperature (DBTT) in Dynamic Small Punch Test

Journal of Testing and Evaluation, 1992
Abstract A dynamic small punch test technique is demonstrated for measuring the ductile-brittle transition temperature (DBTT) of aged Cr-Mo-V turbine rotor steels. Based on fracture energy measurements and fracture surface observations it is shown that the dynamic small punch test specimens exhibit a clear ductile-brittle transition ...
Y-H Joo, T Hashida, H Takahashi
openaire   +1 more source

Effect of small additional elements on DBTT of V–4Cr–4Ti irradiated at low temperatures

Journal of Nuclear Materials, 1998
Abstract As a part of a program to screen several V–4Cr–4Ti containing Si, Al and Y alloys and optimize the amounts of Si, Al and Y, the Charpy impact test of five kinds of V–4Cr–4Ti–Si–Al–Y alloys by an instrumented Charpy impact testing machine using miniaturized specimens (1.5 mm × 1.5 mm × 20 mm) have been conducted before and after neutron ...
Tamaki Shibayama   +3 more
openaire   +1 more source

Experimental and FEA Investigations on the Fracture Properties of Pipe Structures Under Internal Pressure in DBTT Region

Journal of Pressure Vessel Technology, 2009
The fracture behavior of pipes with penetrating cracks was experimentally investigated with the results of the load-deflection curves and crack length. J-R curves were obtained from the testing results for different temperatures. With the decrement in temperature, the critical J integral decreases and the tearing modulus increases. An updated continuum
Zhao-Xi Wang   +3 more
openaire   +1 more source

Applicability of a Deterministic Approach to Transfer the Minimum Fracture Toughness Between Different Temperatures in the DBTT Region

Volume 3: Design and Analysis, 2016
In this paper, we demonstrate that a deterministic approach requiring only tensile test data for different temperatures has a possibility to predict the minimum fracture toughness for these temperatures. The material is assumed to be in the Ductile-to-Brittle-Transition Temperature (DBTT) region.
Toshiyuki Meshii   +2 more
openaire   +1 more source

Evaluation of fracture toughness and its scatter in the DBTT region of different types of pressure vessel steels

Engineering Failure Analysis, 2011
Abstract Safety analysis of critical components and the overall plant is a major and important task in the field of mechanical engineering. Therefore, it is essential to know the allowable loads and the corresponding failure behaviour (e.g., crack initiation, growth and instability) of the component.
M.K. Samal   +3 more
openaire   +1 more source

Effect of Location of V-Notch on Neutron Irradiation-Induced Shift in DBTT of HAZ of Welded Pressure Vessel Steel

2000
The effect of the location of the V-notch in the heat affected zone (HAZ) on the ductile-brittle transition behavior of neutron-irradiated welded A533B pressure vessel steel has been investigated utilizing the small specimen technique. Standard size, one-third size and 1.5 mm size Charpy V-notch specimens were prepared by changing the distance from the
T Suzuki   +4 more
openaire   +1 more source

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