报告一: R&D on fusion materials at SCK-CEN (Belgian Nuclear Research Centre)

报告人：Dmitry Terentyev, Department of Civil and Environmental Engineering, SCK-CEN, Belgium

主持人：段慧玲 教授

时  间：11月17日（周二）中午12:30—13:30

地  点：澳门太阳娱乐网站官网1号楼210会议室

报告内容简介：

The presentation will overview the R&D activities carried out over the last decade at Belgium Nuclear Research Centre (SCK-CEN). The major activities are concerned with the investigation of structural materials and plasma-facing materials for applications in ITER and DEMO. With respect to structural materials, the low temperature embrittlement of high-Cr steels (Eurofer) is of primary concern and it was addressed by combined experimental and modeling approaches, building up the whole multi-scale modeling pyramid of tools to predict the mechanical behavior starting from fundamental investigations. As what concerns the plasma-facing materials, tungsten and tungsten-based alloys are the primary materials under investigations. The focus of SCK-CEN in that respect is made on the understanding on high temperature deformation mechanisms, surface cracking under contact with high flux plasma, and microstructural evolution under plasma and neutron exposure. The presentation will review the above mentioned topics with an emphasis on physical origin and technological issues raising upon characterization and testing of the fusion materials.

报告人简介：

Dr. Dmitry Terentyev was born in 1979 in Leningrad (now St. Petersburg) Soviet Union He graduated at Polytechnic University of St. Petersburg (Russian Federation) at the department of Physical Mechanical Engineering in 2002. In the period of 2002-2006 he accomplished PhD at University Libre de Bruxelles (Belgium) working on the "Modeling of Radiation Damage in high-Cr steels for Fusion Applications". In 2007, he was employed as researcher at Belgian Nuclear Research Centre as responsible for the atomistic modeling activities in fusion and fission structural materials. In 2014, he became a Head of Fusion Research Unit at Belgian Nuclear Research Centre

 

报告二:  In situ characterization of defect-twin boundary interactions under heavy ion irradiation

报告人：Kaiyuan Yu, Department of Materials Science and Engineering, China University of Petroleum-Beijing

主持人：段慧玲 教授

时  间： 11月17日（周二）下午13:45—14:45

地  点：澳门太阳娱乐网站官网1号楼210会议室

报告内容简介：

Twin boundaries enable excellent mechanical, physical properties in nanotwinned metals. We present that twin boundaries can also enhance the radiation tolerance of FCC metals. Ag with high density nanoscale twins were in situ irradiated by Kr ions using IVEM facility at Argonne National Laboratory. A large number of stacking fault tetrahedra are removed during their interactions with abundant coherent twin boundaries. Consequently the density of stacking fault tetrahedra in irradiated nanotwinned Ag is significantly lower than that in its coarse-grained counterpart. The interaction mechanisms are discussed and compared to predictions by molecular dynamics simulations. In situ studies also reveal two new phenomena: 1. Radiation induced frequent migration of coherent and incoherent twin boundaries; 2. Self-healing of coherent twin boundaries where defect denuded zones are observed. Such twin boundary behavior is also correlated to the defect-twin boundary interactions. Furthermore, the migration of twin boundaries under irradiation leads to the shrinkage of pre-existed nanovoids in nanotwinned Cu, underscoring the potential of nanotwinned metals in nuclear energy applications.

报告人简介：

Dr. Kaiyuan Yu is currently an associate professor at the Department of Materials Science at China University of Petroleum-Beijing. Dr Yu holds a bachelor degree (2006) and a master degree (2009) with Beihang University (Beijing, China). He was awarded a doctoral degree of materials science and engineering by Texas A&M University (College Station, TX, US) in 2013. Later, Dr. Yu worked for the Department of Mechanical Engineering at Texas A&M as a lecturer and for the Department of Electrical and Computer Engineering at Texas A&M as a post-doctoral associate before he joined China University of Petroleum-Beijing in July 2014. The research interests of Dr. Kaiyuan Yu include radiation damage in solids, dynamic characterization of defect-interface coupling under radiation and mechanical properties of nanocomposite materials. He has published more than 20 peer-reviewed papers which has been cited over 230 times, and chaired 6 symposiums at MRS and TMS conferences.

欢迎广大师生光临！