Plan and strategy for ITER blanket testing in Japan

Mikio Enoeda, Masato Akiba, Satoru Tanaka, Akihiko Shimizu, Akira Hasegawa, Satoshi Konishi, Akihiko Kimura, Akira Kohyama, Akio Sagara, Takeo Muroga

Research output: Contribution to journalArticlepeer-review

4 Citations (Scopus)


The Fusion Council of Japan has established the long-term program for the development of blanket in 1999. In the program, the solid breeder blanket was selected as the primary candidate blanket of the fusion power demonstration plant in Japan, while liquid breeder blankets and high temperature solid breeder blanket have been identified as the attractive advanced blanket. Japan Atomic Energy Research Institute (JAERI) is leading the development of solid breeder blankets, while, universities and National Institute for Fusion Science (NIFS) are developing the advanced blankets for potential options of the fusion power demonstration plant and commercial power plants. ITER blanket module testing is regarded as one of the most important milestones, by which integrity of candidate blanket design is qualified for the fusion power demonstration plant, together with material irradiation data by International Fusion Material Irradiation Facility (IFMIF). Japan is investigating the possibility of testing all types of blankets under TBWG framework with both of JAERI and universities/NIFS involvements. This paper presents a plan and strategy for the development of test blanket modules and ITER blanket module testing in Japan.

Original languageEnglish
Pages (from-to)1023-1030
Number of pages8
JournalFusion Science and Technology
Issue number4
Publication statusPublished - 2005 May

ASJC Scopus subject areas

  • Civil and Structural Engineering
  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering


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