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Dive into the research topics where Jiachao Chen is active.

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Featured researches published by Jiachao Chen.


Philosophical Magazine | 2007

Discrete dislocation dynamics simulations of dislocation interactions with Y2O3 particles in PM2000 single crystals

Boton Bakó; D. Weygand; M. Samaras; Jiachao Chen; Manuel A. Pouchon; Peter Gumbsch; Wolfgang Hoffelner

In oxide dispersion strengthened steels the interactions between dispersoids and dislocations determine the materials plasticity. Using three-dimensional Discrete Dislocation Dynamics simulations, the effect of Y2O3 dispersoids on the motion of dislocations in BCC single crystal PM2000, a commercial alloy candidate for gas-cooled reactors, has been studied. The dispersoid distribution used in this model has been derived from experimental TEM observations of PM2000. As screw dislocations are predominant in the studied material, the behaviour of a single screw dislocation under shear loading in a distribution of spherical Y2O3 dispersoids is studied. The critical resolved shear stress, the minimum value of the external stress needed to move the dislocation through the obstacle field, is found to be only slightly lower than the experimentally determined value revealing that dispersoids are the main hardening contributions.


Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2 | 2008

Condition Monitoring of High Temperature Components With Sub-Sized Samples

Wolfgang Hoffelner; Manuel A. Pouchon; M. Samaras; Annick Froideval; Jiachao Chen

Advanced nuclear plants are designed for long-term operation in quite demanding environments. Limited operation experience with the materials used in such plants necessitate a reliable assessment of damage and residual life of components. Non-destructive condition monitoring of damage is difficult, if not impossible for many materials. Periodic investigation of small samples taken from well defined locations in the plant could provide an attractive tool for damage assessments. This paper will discuss possibilities of using very small samples taken from plant locations for complementary condition monitoring. Techniques such as micro/nano-indentation, micropillar compression, micro bending, small punch and thin strip testing can be used for the determination of local mechanical properties. Advanced preparation techniques such as focused ion beam (FIB) allow the preparation of samples from these small volumes for micro-structural analyses with transmission electron microscope (TEM) and advanced X-ray synchrotron techniques. Modeling techniques (e.g. dislocation dynamics DD) can provide a quantitative link between microstructure and mechanical properties. Using examples from ferritic oxide dispersion strengthened materials the DD approach is highlighted to understand component life assessments.


Advanced Materials Research | 2008

Microcharacterization of Damage in Materials for Advanced Nuclear Fission Plants

Manuel A. Pouchon; Jiachao Chen; Wolfgang Hoffelner

Miniature and sub-miniature samples were used for determination of mechanical properties of materials for advanced fission plants. Results from indentation and focused ion beam prepared micro-samples, punch tests and thin strip (irradiation) creep tests are shown. The results allow conclusions concerning materials damage. Irradiation damage profiles were determined with indentation. Results from micro-pillar tests showed a good agreement with results from conventional samples in case of oxide dispersion strengthened steels. Thin strip irradiation creep experiments revealed a negligible influence of dispersoid size/distribution on creep rates. Punch tests of fibre reinforced materials showed consistent results which still need quantitative analysis.


Experimental Mechanics | 2010

Characterization of Irradiation Damage of Ferritic ODS Alloys with Advanced Micro-Sample Methods

Manuel A. Pouchon; Jiachao Chen; Rudy Ghisleni; Johann Michler; Wolfgang Hoffelner


Journal of Nuclear Materials | 2009

Irradiation creep and microstructural changes in an advanced ODS ferritic steel during helium implantation under stress

Jiachao Chen; Manuel A. Pouchon; Akihiko Kimura; P. Jung; Wolfgang Hoffelner


Journal of Nuclear Materials | 2009

Irradiation creep of oxide dispersion strengthened (ODS) steels for advanced nuclear applications

Jiachao Chen; Wolfgang Hoffelner


Journal of Nuclear Materials | 2006

Oxide dispersion strengthened steel irradiation with helium ions

Manuel A. Pouchon; Jiachao Chen; M. Döbeli; Wolfgang Hoffelner


Journal of Nuclear Materials | 2008

Irradiation creep and precipitation in a ferritic ODS steel under helium implantation

Jiachao Chen; P. Jung; Manuel A. Pouchon; Tomislav Rebac; Wolfgang Hoffelner


Metallurgical and Materials Transactions A-physical Metallurgy and Materials Science | 2009

Thermal and Irradiation Creep Behavior of a Titanium Aluminide in Advanced Nuclear Plant Environments

Jiachao Chen; Wolfgang Hoffelner


Metallurgical and Materials Transactions A-physical Metallurgy and Materials Science | 2008

Synchrotron X-Rays for Microstructural Investigations of Advanced Reactor Materials

Wolfgang Hoffelner; Annick Froideval; Manuel A. Pouchon; Jiachao Chen; M. Samaras

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M. Samaras

Paul Scherrer Institute

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M. Döbeli

Paul Scherrer Institute

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P. Jung

Forschungszentrum Jülich

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Boton Bakó

Paul Scherrer Institute

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Joerg Raabe

Paul Scherrer Institute

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