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TOPIC B - Blanket Technology
P1A1 - Overview of the design activities of the EU DEMO Helium Cooled Pebble Bed breeding blanket
Guangming Zhou
P1A2 - Accelerating stellarator reactor engineering: design and integration of the Dual Coolant Lithium Lead Breeding Blanket for HELIAS
Iole Palermo
P1A3 - Preparing for the First Integrated Test of a Fusion Breeding Blanket Prototype in the CHIMERA Facility
Thomas R. Barrett
P1A4 - Structural Integrity Assessment of the Central Outboard Segment of the EU DEMO HCPB Breeding Blanket
Anoop Retheesh
P1A5 - Development of the high temperature PbLi experimental loop for CFETR
Kecheng Jiang
P3A1 - Overview of Progress on Water Cooled Ceramic Breeder Blanket in Japan
Yoshinori Kawamura
P3A2 - Alternative water-cooled breeding blanket concepts for the EU DEMO: Overview on studies and perspectives
Francisco Hernández
P3A4 - Challenges of the High Heat Flux loaded Helium Cooled First Wall, Contributions of Numerical Flow Simulations
Christine Klein
P3A5 - Multiphysics tritium transport modelling in WCLL breeding blankets: Influence of MHD effects and neutron damage
James Dark
P4A1 - Plan on Breeding Blanket Test Facility for DEMO in Korea
Mu-Young Ahn
P4A2 - Perspectives of a DCLL blanket for a future strong magnetic field fusion device
Sergey Smolentsey
P4A3 - Progress in the Conceptual Design of the Supercritical CO2 Cooled Lithium-Lead Blanket and the Power Conversion System for CFETR
Lei Chen
P4A4 - Embrittlement of WCLL Blanket and Its Fracture Mechanical Assessment
Jarir Aktaa
P4A5 - An integral methodological framework for the thermo-mechanical analysis and structural integrity assessment of the European TBM Sets
Eduardo RodrÃguez
P5A1 - Progress on Blanket Technology Development in China
Xiaoyu Wang
P5A2 - Study on the tritium breeding characteristic of solid blankets of fusion reactors
Shen Qu
P5A3 - Electrical properties of ceramic coatings after heavy-ion irradiation and lithium implantation
Takumi Chikada
P5A4 - A Liquid Metal Blanket Concept with the First Wall Covered by the Liquid Metal Surface Flow for the Helical Fusion Reactor HESTIA
Junichi Miyazawa
P5A5 - Design and construction of a helium cooling experimental loop for tritium blanket
Xingfu Ye
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