ICFRM-18

SPECIAL INTRODUCTORY SESSION (TUTORIAL SEMINAR)

We are pleased to announce a special introductory session scheduled in the afternoon of November 5th (Sunday). This session is aimed to provide an opportunity to obtain comprehensive knowledge about the overview and history of fusion materials research from both scientific and engineering viewpoints. The following three lectures are planned; each one of them has an hour for lecture and discussion. Although this session was originally planned as a tutorial session for students in previous series of ICFRM, we believe that our lecturers will deliver insightful lectures, instructive not only for students but also for specialists, as they always do so.

Date: Sunday, November 5, 2017
Time: 13:30 to 17:00 (registration will open at 13:00.)
Location: WA-RASSE, Event Hall (capacity is up to 180 with no tables)
Registration: free (included in the conference registration fee)
Program:

Time Lecturer Topic
13:45-14:45 Anton Möeslang
(Karlsruhe Institute of Technology, Germany)
Overview of current reactor design and structural materials
15:30-16:30 Steven J. Zinkle
(University of Tennessee, United States)
Fundamentals of radiation effects in materials
16:45-17:45 Takeshi Hirai
(ITER, France/Japan)
ITER plasma-facing components, materials, design and manufacturing technologies

The entrance of Event Hall is located on the 2nd floor (one floor up from the ground level). The reception desk is also located there.

Lectures

Overview of current reactor design and structural materials

by Prof. Anton Möslang

Karlsruhe Institute of Technology, Germany
Prof. Anton Möslang

Typical examples of fusion reactor designs providing electricity to the grid will be shown and the challenging requirements for structural materials derived from different blanket and divertor solutions will be reviewed. High temperature and neutron damage resistant materials are required, featuring low activation capability and high irradiation tolerance. Furthermore the realization of a power reactor will depend on proven fabrication and joining technologies, materials compatibility and validated structural design rules. Therefore, a qualified materials database is indispensable. According to the different functions, structural materials for reference blankets are based on reduced activation ferritic (martensitic) steels, including oxide dispersion strengthened variants, while for divertor applications, refractory based structural materials and laminates and in some cases CuCrZr and Vanadium alloys are most promising presently. For neutron irradiated reduced activation steels and nanoscaled ODS-alloys dpa and He/dpa specific correlations are made between mechanical properties and microstructure. Finally, conclusions are drawn regarding design windows and the microstructural engineering of irradiation tolerant materials.

Biography

Prof. Dr. Anton Möslang is head of the Institute for Applied Materials – Applied Materials Physics at KIT Karlsruhe since 2011 and is lecturing at the Faculty of Mechanical Engineering since 2005. 1996 he became elected member of the Scientific Technical Advisory Board of FZK Karlsruhe and in 2009 of the KIT Senate. Prior to 2011, he had leading roles in the development of the “International Fusion Materials Irradiation Facility, IFMIF”, and was member of several advisory boards of large-scale infrastructures, European research organizations and in the organization of international conference series. In 1984, he obtained a PhD at the University of Konstanz in the field Solid State Physics with nuclear methods. Presently Anton Möslang is mainly responsible for the development and qualification of neutron tolerant and high temperature resistant advanced structural materials, mostly for nuclear fission and fusion but also for other carbon dioxide free applications with modern methods of the materials science.


Fundamentals of Radiation Effects in Materials

by Prof. Steven J. Zinkle

University of Tennessee
Prof. Steven J. Zinkle

The neutron irradiation environment associated with deuterium-tritium fusion energy reactors represents an extremely harsh operating environment for the construction materials. Energetic particle irradiation can induce pronounced microstructural and property changes in materials. The high levels of neutron-induced generation of helium and hydrogen can induce additional degradation processes in materials. This presentation will provide an overview of radiation-induced microstructural and property changes in materials. There are several key temperature regimes for all irradiated materials (defined by the onset temperatures for migration of interstitials and vacancies, thermal dissolution of in-cascade produced vacancy clusters, and thermal evaporation of cavities). In general, radiation tolerance in one temperature regime does not universally translate to radiation tolerance in other temperature regimes due to different controlling physical parameters. The fluence dependence of defect accumulation also is generally significantly different in the various temperature regimes. The roles of primary knock on atom energy, damage rate, and He/dpa generation rate will be discussed.

Biography

Dr. Zinkle is a UTK/ORNL Governor’s Chair Professor in the Nuclear Engineering and Materials Science & Engineering Departments at the University of Tennessee, Knoxville (UTK), with a joint appointment at Oak Ridge National Laboratory (ORNL). Prior to 2013, he served in a variety of management and technical R&D roles at ORNL including Chief Scientist of the Nuclear Science and Engineering Directorate, director of the Materials Science and Technology Division, and ORNL Corporate Fellow. Much of his research has utilized materials science to explore fundamental physical phenomena that are important for advanced nuclear energy applications, focusing on microstructure-property relationships. He received his PhD in Nuclear Engineering and an MS in Materials Science from the University of Wisconsin-Madison in 1985. He has written over 260 peer-reviewed publications, and is a fellow of the American Nuclear Society, TMS (The Minerals, Metals & Materials Society), ASM International, the American Ceramic Society, the Materials Research Society, the American Physical Society, and AAAS. He is a member of the US National Academy of Engineering.


ITER Plasma-Facing Components, materials, design and manufacturing technologies

by Dr. Takeshi Hirai

ITER Organization
Dr. Takeshi Hirai

Plasma-facing components in Fusion reactors are subjected to high heat, high particle flux and high electromagnetic loads. The selection of appropriate materials is essential. In ITER, tungsten, beryllium, copper alloy and steels are selected as main materials for plasma-facing components. Furthermore, design to meet the requirements as well manufacturing technology are essential. These topics particularly, for ITER application, are discussed.

Biography

Dr Hirai is currently working in the Divertor section at the ITER Organization since 2008 and he is in charge of procurement of the ITER Divertor vertical target as well he led the full-tungsten ITER Divertor design activity as the task force leader at the ITER Organization. He was involved in tokamak plasma exposure experiments, high heat flux testing and characterization of plasma-facing components and materials at Jülich research centre, Germany. During this appointment (2000-2008), he led the JET bulk tungsten Divertor design activity as the technical coordinator; furthermore, he was also involved in European DEMO Divertor design activity. He obtained doctor degree of engineering from Kyushu University Japan in 2000. He has been working extensively in the international fusion community for around 20 years and he published over one hundred peer-reviewed publications on high heat flux and particle exposure tests, and component design.

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