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Thermal analysis and optimization of the new ICRH antenna Faraday Screen in EAST

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초록

In Experimental Advanced Superconducting Tokamak (EAST) experiments, to achieve long pulse and high-power ICRH system operation, a new kind of ICRH antenna has been designed. One of the most critical factors in limiting the operation of long pulse and high power is the intense heat load in the front face of the ICRH antenna, especially the Faraday Screen (FS). Therefore, the cooling channels of FS need to be designed. According to thermal-hydraulic analysis, the FS tubes are divided into several groups to achieve more excellent water cooling capability. The number of series and parallel tubes in one group is chosen as six. This antenna went into service in the spring of 2021, and it is delightful that the temperature distribution of the FS tube is below 400 C in 14.5 s and 1.8 MW ICRH system operation. However, the active water-cooling design was not carried out on the upper and lower plates of FS, which led to severe ablations on that region under long pulse and high power operation, and the temperature is up to 800. Therefore, the upper and lower side plates of the FS were designed with water cooling based on thermal-hydraulic analysis. During the 2022 winter experiments, the temperature of ICRH antenna FS was lower than 400 in the pulse of 200s and the power of 1 MW operation.

Abstract

In Experimental Advanced Superconducting Tokamak (EAST) experiments, to achieve long pulse and high-power ICRH system operation, a new kind of ICRH antenna has been designed. One of the most critical factors in limiting the operation of long pulse and high power is the intense heat load in the front face of the ICRH antenna, especially the Faraday Screen (FS). Therefore, the cooling channels of FS need to be designed. According to thermal-hydraulic analysis, the FS tubes are divided into several groups to achieve more excellent water cooling capability. The number of series and parallel tubes in one group is chosen as six. This antenna went into service in the spring of 2021, and it is delightful that the temperature distribution of the FS tube is below 400 C in 14.5 s and 1.8 MW ICRH system operation. However, the active water-cooling design was not carried out on the upper and lower plates of FS, which led to severe ablations on that region under long pulse and high power operation, and the temperature is up to 800. Therefore, the upper and lower side plates of the FS were designed with water cooling based on thermal-hydraulic analysis. During the 2022 winter experiments, the temperature of ICRH antenna FS was lower than 400 in the pulse of 200s and the power of 1 MW operation.

참고문헌 (11)

  1. B. Wan, "Collaborators", Nucl. Fusion, 53, pp.104006~ (2013)
  2. X. J. Zhang, , Nucl. Fusion, 52, pp.032002~ (2012)
  3. X.J. Zhang, , AIP Conf. Proc, 2260, pp.030004~ (2020)
  4. J. H. Wang, , Plasma Sci. Technol, 20, pp.045603~ (2018)
  5. L. N. Liu, , Rev. Sci. Instrum, 90, pp.063504~ (2019)
  6. K. Saito, , Fusion Eng. Des, 154, pp.111496~ (2020)
  7. X. Zhang, , Nucl. Fusion, 62, pp.086038~ (2022)
  8. Liu L.N., "Measurement of the ICRH antenna phasing using antenna strap probe based diagnostic system in EAST tokamak", Nuclear Engineering and Technology, 54(10), pp.3614~3619 (2022), 한국원자력학회[DOI]
  9. M. S. T. Berruti, , Fuel Energy Abstr, 47, pp.210~ (2006)
  10. Z. Chen, , Fusion Eng. Des, 94, pp.82~89 (2015)
  11. S. Dai, "And the LHD experimental group", Plasma Phys. Contr. Fusion, 59, pp.085013~ (2017)

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