일시: 2022년 5월 25일 (수) 21:00 (CET)

주제: Overview of Fusion, ITER, Tritium Breeding Technology

발표자: 김병윤 박사님

Short Bio:
Dr B.Y. Kim is the mechanical responsible officer of the TBM port plug design and
manufacture at ITER Organization since Jan 2012. He has developed the FEM based
shakedown analysis for plasma facing components to predict safety limit during his PhD in
Max-Planck-Institute for Plasma Physics (IPP) and Technische Universitaet in Muenchen.
Before joining ITER Organization, he worked for R&D center of Hyundai-Kia Mortors (2005-
2008) as senior research engineer to develop new materials and processing. After he joined
National Fusion Research Institute (2008-2011) as technical responsible officer for ITER
blanket first wall and neutral beam duct liner, and vacuum vessel support. He has extensive
experience on the design and engineering of fusion components.

Abstract:

ITER is a large-scale scientific experiment that aims to demonstrate that it is possible to
produce commercial energy from fusion. During its operational lifetime, ITER will test key
technologies necessary for the next step: the demonstration fusion power plant that will prove
that it is possible to capture fusion energy for commercial use. Tritium Breeding Blanket
(TBB) ensuring tritium breeding self-sufficiency is a compulsory element for a demonstration
power reactor (DEMO), the next-step after ITER. Although a TBB is not required for ITER,
since it will procure the tritium from external sources, it is included among the ITER missions
that “ITER should test tritium breeding module concepts that would lead in a future reactor to
tritium self-sufficiency, the extraction of high grade heat and electricity production”. All
activities related to this mission correspond to the so-called “ITER TBM Program”. A
successful ITER TBM Program represents an essential step for any fusion power development
plan of all the seven ITER Members (IMs). In this presentation, ITER and TBM Programs are
briefly introduced.

첨부파일: [VeKNI2022_Webinar]Byoung-Yoon_Kim_OverviewOfFusion-ITER-TritiumBreedingTechnology_Abstract_20220525 .pdf