Neutronics analysis for a compact reversed shear tokamak CREST

Q. Huang, S. Zheng, L. Lu, R. Hiwatari, Y. Asaoka, K. Okano, Y. Ogawa

研究成果: Conference article査読

17 被引用数 (Scopus)


The compact reversed shear tokamak CREST is a conceptual tokamak reactor design with high β plasma, high thermal efficiency, competitive cost and water-cooled ferritic steel components. In this manuscript neutronics analysis on CREST is presented based on the three-dimensional (3D) model and calculations by MCNP/4C code and FENDL/2.0 data library. The comparison among the results of tritium breeding ratio (TBR) for the one-dimensional (1D), two-dimensional (2D) and 3D calculations shows that the results are consistent with each other. The system would be tritium self-sufficient when considering the blanket coverage fraction, etc. and even some uncertainty. It has an energy multiplication of 1.38. The maximum neutron wall loading and maximum damage rate at the first wall (FW) are 6.30 MW/m2 and 51.9 dpa/FPY, respectively. The FW material needs to be replaced every 3.8 years of operation with an availability of 75% if the neutron damage of ferritic steel is assumed to limit to 150 dpa. The total nuclear heat for TF coils is under the limit for TF coils in ITER case. The nuclear heat density for TF coils at the mid-plane is roughly the same as the limit for ITER.

ジャーナルFusion Engineering and Design
8-14 PART B
出版ステータスPublished - 2006 2
イベントProceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B -
継続期間: 2005 5 222005 5 27

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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