Published June 2005 | Version v1
Journal article

Present status of ITER test blanket development

  • 1. Tokyo Univ., Tokyo (Japan)
  • 2. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
  • 3. Tohoku Univ., Sendai, Miyagi (Japan)
  • 4. Kyoto Univ., Kyoto (Japan)
  • 5. National Inst. for Fusion Science, Toki, Gifu (Japan)

Description

As one of the engineering test programs in ITER, the test blanket program, which utilizes ITER as a test bed to develop breeding blanket systems for fusion DEMO plants, has been planned and advanced. The Test Blanket Working Group (TBWG) has been organized to review and coordinate test programs on Test Blanket Modules (TBM). Five breeding blanket concepts have been proposed and discussed in the TBTG, and Japan is participating in the development of all of these concepts. This paper describes the status of TBM design, blanket technology and materials development for ITER TBMs. The current design and R and D status of candidate TBM concepts, which include 1) a water-cooling system with a solid breeder, 2) a helium gas-cooling system with a solid breeder, 3) a lithium-lead (LiPb) breeding system, 4) a liquid lithium breeding system, and 5) a molten salt breeding system, are presented and discussed. (author)

Additional details

Publishing Information

Journal Title
Purazuma, Kaku Yugo Gakkai-Shi
Journal Volume
81
Journal Issue
6
Journal Page Range
p. 434-450
ISSN
0918-7928

Optional Information

Notes
41 refs., 22 figs., 4 tabs.