Design study of blanket structure based on a water-cooled solid breeder for DEMO

Youji Someya, Kenji Tobita, Hiroyasu Utoh, Shinji Tokunaga, Kazuo Hoshino, Nobuyuki Asakura, Makoto Nakamura, Yoshiteru Sakamoto

研究成果: Article査読

36 被引用数 (Scopus)


Blanket concept with a simplified interior for mass production has been developed using a mixed bed of Li2TiO3 and Be12Ti pebbles, coolant conditions of 15.5 MPa and 290-325 °C and cooling pipes without any partitions. Considering the continuity with the ITER test blanket module option of Japan and the engineering feasibility in its fabrication, our design study focused on a water-cooled solid breeding blanket using the mixed pebbles bed. Herein, we propose blanket segmentation corresponding to the shape and dimension of the blanket and routing of the coolant flow. Moreover, we estimate the overall tritium breeding ratio (TBR) with a torus configuration, based on the segmentation using three-dimensional (3D) Monte Carlo N-particle calculations. As a result, the overall TBR is 1.15. Our 3D neutronics analysis for TBR ensures that the blanket concept can achieve a self-sufficient supply of tritium.

ジャーナルFusion Engineering and Design
出版ステータスPublished - 2015 10月 1

ASJC Scopus subject areas

  • 土木構造工学
  • 原子力エネルギーおよび原子力工学
  • 材料科学(全般)
  • 機械工学


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