Author/Authors :
Cho، نويسنده , , Seungyon and Ahn، نويسنده , , Mu-Young and Lee، نويسنده , , Dong Won and Park، نويسنده , , Yi-Hyun and Lee، نويسنده , , Eo Hwak and Yoon، نويسنده , , Jae Sung and Kim، نويسنده , , Tae Kyu and Lee، نويسنده , , Cheol-Woo and Yoon، نويسنده , , Young-Hoon and Kim، نويسنده , , Suk Kwon and Jin، نويسنده , , Hyung Gon and Shin، نويسنده , , Kyu In and Jung، نويسنده , , Yang Il and Jeong، نويسنده , , Yong-Hwan and Lee، نويسنده , , Yong Ouk and Ku، نويسنده , , Duck Young and Kim، نويسنده , , Chang-Shuk and Park، نويسنده , , Soon Chang and Yu، نويسنده , , In-Keun and Jung، نويسنده , , Kijung، نويسنده ,
Abstract :
Korea plans to install and test Helium Cooled Ceramic Reflector (HCCR) Test Blanket Module (TBM) in the ITER, because the HCCR blanket concept is one of options of the DEMO blanket. Currently, many design and R&D activities have been performed to develop the Korean HCCR TBM. An integrated design tool for a fusion breeder blanket has been developed based on nuclear technologies including a safety analysis for obtaining a license for testing in the ITER. A half-scale sub-module mockup of the first wall with the manifold was fabricated, and the manufacturability and thermo-hydraulic performances were evaluated. High heat load and helium cooling test facilities have been constructed. Next, the recent status of TBM material development in Korea was introduced including Reduced Activation Ferritic Martensitic (RAFM) steel, lithium ceramic pebbles and silicon carbide (SiC) coated graphite pebbles. Several fabrication methods of RAFM steel, lithium ceramic pebbles, and silicon carbide coating on graphite pebbles were investigated. Recent design and R&D progress on these areas are introduced here.
Keywords :
Lithium ceramic breeder , Graphite reflector , Test blanket module (TBM) , Helium Cooled Ceramic Reflector (HCCR)
