Abstract
Japan is performing design and technology developments for the purpose of module testing and contribution to the module development and testing under the framework of Test Blanket Working Group (TBWG) with involvements of all of Japan Atomic Energy Research Institute (JAERI) and universities and National Institute for Fusion Science (NIFS). As the primary blanket option, solid breeder test blanket modules (TBMs) with reduced activation ferritic steel structure is being developed and proposed to be delivered on the first day of ITER operation, mainly by JAERI. As for the advanced blanket options, mainly universities and NIFS have been performing R&D of key technologies and design concept development of solid breeder blanket test article made of SiC composite contained inside the ferritic steel box, liquid LiPb breeder blanket TBM cooled by helium and its dual-coolant option, liquid Li self-cooled blanket TBM and molten salt self-cooled TBM. In all necessary fields of the development of the primary blanket option, the element technology development phase has been almost completed and is now stepping further to the engineering test phase. The development of advanced test blankets is also showing steady progress to overcome key issues toward module testing.
Original language | English |
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Pages (from-to) | 415-424 |
Number of pages | 10 |
Journal | Fusion Engineering and Design |
Volume | 81 A |
Issue number | 1-4 |
DOIs | |
Publication status | Published - 2006 Feb |
Event | Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part A - Duration: 2005 May 22 → 2005 May 27 |
Keywords
- Helium-cooled solid breeder blanket
- Liquid breeder
- Test blanket module
- Water-cooled solid breeder blanket
ASJC Scopus subject areas
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering