Carbon tiles as spectral-shifter for long-life liquid blanket in LHD-type reactor FFHR

A. Sagara, S. Imagawa, T. Tanaka, T. Muroga, Y. Kubota, T. Dolan, H. Hashizume, T. Kunugi, Satoshi Fukada, A. Shimizu, T. Terai, O. Mitarai

研究成果: ジャーナルへの寄稿Conference article

6 引用 (Scopus)

抄録

In terms of engineering feasibility for long-life Flibe blanket in LHD-type reactor FFHR, the Spectral-shifter and Tritium breeder Blanket (STB) concept is evaluated by taking neutron irradiation effects into account under system integration such as Flibe cooling and components replacement. FEM calculations for the neutron wall loading of 1.5 MW/m2 show that the temperature of the STB armor tile can be kept below 2000 K by optimizing the first metal wall thickness. The heat load experiment on the STB armor mockup confirms feasibility of the temperature control and mechanical joining. Degradation of STB armor tiles due to neutron irradiation requires replacement of them every few years by means of remote handling "screw coasters" using helical winding, where the replaced tiles are low level wastes. Although the STB concept is feasible within nuclear and thermal properties, more detailed structural optimization is needed including the mechanical and chemical properties.

元の言語英語
ページ(範囲)1299-1304
ページ数6
ジャーナルFusion Engineering and Design
81
発行部数8-14 PART B
DOI
出版物ステータス出版済み - 2 1 2006
イベントProceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B -
継続期間: 5 22 20055 27 2005

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Tritium
Tile
Carbon
Armor
Liquids
Neutron irradiation
Nuclear properties
Structural optimization
Thermal load
Temperature control
Joining
Chemical properties
Neutrons
Thermodynamic properties
Metals
Cooling
Finite element method
Degradation
Mechanical properties
Experiments

All Science Journal Classification (ASJC) codes

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

これを引用

Sagara, A., Imagawa, S., Tanaka, T., Muroga, T., Kubota, Y., Dolan, T., ... Mitarai, O. (2006). Carbon tiles as spectral-shifter for long-life liquid blanket in LHD-type reactor FFHR. Fusion Engineering and Design, 81(8-14 PART B), 1299-1304. https://doi.org/10.1016/j.fusengdes.2005.09.067

Carbon tiles as spectral-shifter for long-life liquid blanket in LHD-type reactor FFHR. / Sagara, A.; Imagawa, S.; Tanaka, T.; Muroga, T.; Kubota, Y.; Dolan, T.; Hashizume, H.; Kunugi, T.; Fukada, Satoshi; Shimizu, A.; Terai, T.; Mitarai, O.

:: Fusion Engineering and Design, 巻 81, 番号 8-14 PART B, 01.02.2006, p. 1299-1304.

研究成果: ジャーナルへの寄稿Conference article

Sagara, A, Imagawa, S, Tanaka, T, Muroga, T, Kubota, Y, Dolan, T, Hashizume, H, Kunugi, T, Fukada, S, Shimizu, A, Terai, T & Mitarai, O 2006, 'Carbon tiles as spectral-shifter for long-life liquid blanket in LHD-type reactor FFHR', Fusion Engineering and Design, 巻. 81, 番号 8-14 PART B, pp. 1299-1304. https://doi.org/10.1016/j.fusengdes.2005.09.067
Sagara A, Imagawa S, Tanaka T, Muroga T, Kubota Y, Dolan T その他. Carbon tiles as spectral-shifter for long-life liquid blanket in LHD-type reactor FFHR. Fusion Engineering and Design. 2006 2 1;81(8-14 PART B):1299-1304. https://doi.org/10.1016/j.fusengdes.2005.09.067
Sagara, A. ; Imagawa, S. ; Tanaka, T. ; Muroga, T. ; Kubota, Y. ; Dolan, T. ; Hashizume, H. ; Kunugi, T. ; Fukada, Satoshi ; Shimizu, A. ; Terai, T. ; Mitarai, O. / Carbon tiles as spectral-shifter for long-life liquid blanket in LHD-type reactor FFHR. :: Fusion Engineering and Design. 2006 ; 巻 81, 番号 8-14 PART B. pp. 1299-1304.
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AU - Sagara, A.

AU - Imagawa, S.

AU - Tanaka, T.

AU - Muroga, T.

AU - Kubota, Y.

AU - Dolan, T.

AU - Hashizume, H.

AU - Kunugi, T.

AU - Fukada, Satoshi

AU - Shimizu, A.

AU - Terai, T.

AU - Mitarai, O.

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AB - In terms of engineering feasibility for long-life Flibe blanket in LHD-type reactor FFHR, the Spectral-shifter and Tritium breeder Blanket (STB) concept is evaluated by taking neutron irradiation effects into account under system integration such as Flibe cooling and components replacement. FEM calculations for the neutron wall loading of 1.5 MW/m2 show that the temperature of the STB armor tile can be kept below 2000 K by optimizing the first metal wall thickness. The heat load experiment on the STB armor mockup confirms feasibility of the temperature control and mechanical joining. Degradation of STB armor tiles due to neutron irradiation requires replacement of them every few years by means of remote handling "screw coasters" using helical winding, where the replaced tiles are low level wastes. Although the STB concept is feasible within nuclear and thermal properties, more detailed structural optimization is needed including the mechanical and chemical properties.

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