Overview of the ITER TBM program

被引：0
|
作者：
Sheng Q. [1 ]
Wu S. [1 ]
Wang X. [2 ]
Zhao F. [2 ]
Luo X. [2 ]
Qian X. [1 ]
Luo D. [1 ]
机构：
[1] China International Nuclear Fusion Energy Program Execution Center, Beijing
[2] Southwestern Institute of Physics, Chengdu
来源：
He Jishu/Nuclear Techniques | 2022年 / 45卷 / 07期
关键词：
ITER; TBM program; Testing blanket module; Tritium breeding;
D O I：
10.11889/j.0253-3219.2022.hjs.45.070001
中图分类号：
学科分类号：
摘要：
The tritium breeding blanket (TBB) technology is one of the key technologies to be solved and also one of three major issues in the development of fusion reactor in the future. The international thermonuclear experimental reactor (ITER) will be the first nuclear fusion experimental reactor in the world whilst ITER test blanket module (TBM) program is the only way to test and validate the tritium breeding blanket technologies under a real fusion environment at present. The successful implementation of ITER TBM program will provide a solid scientific and engineering foundation for fusion energy development. This paper briefly introduces the content, necessity, strategy, organizing and implementation of ITER TBM program, and summarizes the development status and achievement of test blanket system (TBS) made by the participants of ITER members. Prospects of the TBS research activities for the next phase and subsequent research focuses are presented. It is expected to provide valuable references for tritium breeding blanket design and development of China fusion engineering test reactor (CFETR), as well as the development of the TBB technologies. © 2022 Science Press. All rights reserved.
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共 26 条
  • [21] Aubert J, Aiello G, Alonso D, Et al., Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER, Fusion Engineering and Design, 160, (2020)
  • [22] Tincani A, Arena P, Bruzzone M, Et al., Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System, Fusion Engineering and Design, 167, (2021)
  • [23] Zmitko M, Vladimirov P, Knitter R, Et al., Development and qualification of functional materials for the European HCPB TBM[J], Fusion Engineering and Design, 136, pp. 1376-1385, (2018)
  • [24] Cho S, Ahn M Y, Choi J H, Et al., Investigation of technical gaps between DEMO blanket and HCCR TBM [J], Fusion Engineering and Design, 136, pp. 190-198, (2018)
  • [25] Cho S, Ahn M Y, Chun Y B, Et al., Status of HCCR TBM program for DEMO blanket, Fusion Engineering and Design, 171, (2021)
  • [26] Gaincarli L., Report from the re-established test blanket working group (TBWG) for the period of the ITER Transitional Arrangement (ITA), (2005)
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