DOI QR코드

DOI QR Code

Neutronics analysis of the ion cyclotron resonance heating antenna of the China Fusion Engineering Test Reactor

  • Gaoxiang Wang (Institute of Plasma Physics, Hefei Institutes of Physical Science, Chinese Academy of Sciences) ;
  • Chengming Qin (Institute of Plasma Physics, Hefei Institutes of Physical Science, Chinese Academy of Sciences) ;
  • Shanliang Zheng (Institute of Plasma Physics, Hefei Institutes of Physical Science, Chinese Academy of Sciences) ;
  • Yongsheng Wang (Institute of Plasma Physics, Hefei Institutes of Physical Science, Chinese Academy of Sciences) ;
  • Kun Xu (Institute of Plasma Physics, Hefei Institutes of Physical Science, Chinese Academy of Sciences) ;
  • Huiqiang Ma (State Power Investment Group Science and Technology Research Institute)
  • Received : 2023.11.08
  • Accepted : 2024.03.17
  • Published : 2024.08.25

Abstract

Ion cyclotron resonance heating (ICRH) is an important auxiliary heating method applied to the China Fusion Engineering Test Reactor, which can effectively heat the ions and electrons in plasma. Owing to the harsh nuclear environment, neutronic analyses are required to verify tritium self-sufficiency and neutron-shielding requirements. In this study, a neutronics analysis of the ICRH antenna was conducted using the COre and System integrated engine for Reactor Monte Carlo (cosRMC) code to estimate the neutron flux, radiation damage, nuclear heating, gas generation rate of key components, and tritium breeding ratio (TBR), providing data support for the subsequent optimization of the shielding design. In addition, the neutron flux of the coils around the antenna was calculated to prevent the entry of neutrons that damage the magnetic field coils through the gaps between the port plugs and antenna, and the shielding effects of the port-plug antenna on the surrounding components were analyzed. Finally, the results obtained using the cosRMC and MCNP codes were compared, which and presented good agreement, thus verifying the reliability of the neutronic analysis using the cosRMC code.

Keywords

Acknowledgement

The authors thank the technical staff of the EAST group at the Institute of Plasma Physics, China for their support during this work, and the State Power Investment Corporation Limited, China for providing software support. This work was supported by the National Natural Science Foundation of China under Grant Nos. 12105184, 11975265, and 12175273; the National Key Research and Development Program of China under Grant Nos. 2019YFE03070000, 2019YFE03070003, and 2022YFE03190200; and the Comprehensive Research Facility for Fusion Technology Program of China under Contract No. 2018-000052-73-01-001228.

References

  1. Y. Wan, J. Li, Y. Liu, X. Wang, V. Chan, C. Chen, X. Duan, P. Fu, X. Gao, K. Feng, et al., Overview of the present progress and activities on the CFETR, Nucl. Fusion 57 (10) (2017) 102009.
  2. L. Yu, X. Liu, X. Gao, F. Wu, J. Zhu, D. Wang, S. Hong, L. Zeng, J. Li, Progress in the electromagnetic optimization of the CFETR CS coil, Fusion Eng. Des. 192 (2023) 113827.
  3. L. Hu, Y. Liu, et al., Progress of engineering design of CFETR diagnostics, Fusion Eng. Des. 155 (2020) 111731.
  4. M.R. Gilbert, Nuclear data for fusion: Inventory validation successes and future needs, J. Phys.: Energy (2023).
  5. W. Zhang, Q. Liang, C. Qin, X. Zhang, Y. Wang, H. Yang, L. Liu, G. Zhu, Y. Mao, S. Yuan, et al., Conceptual design and optimization of an ITER-type ICRF antenna on CFETR, Nucl. Fusion 62 (7) (2022) 076045.
  6. C.M. Qin, J. Li, X.J. Zhang, et al., "ICRF SYSTEM ON CFETR" 24th topical conference on radio-frequency power in plasmas, 2022.
  7. H. Du, P. Lu, S.-C. Liu, Y. Qin, Y. Yan, Y. Sun, Y. Chen, S. Liu, Benchmark of cosRMC with CFETR fusion neutronics model, Fusion Eng. Des. 144 (2019) 57-61.
  8. X.M.C. Team, MCNP a general Monte Carlo n particle transport code, vesion 5 vol. I: Overview and theory, in: Los Alamos National Laboratory report la-UR-03-1987[file MCNP5 manual VOL I.pdf], April 2003, revised 2/1/2008.
  9. X. Zhang, S. Liu, Y. Yan, Y. Qin, Y. Chen, Application of the neutron-photonelectron coupling transport of cosRMC in fusion neutronics, Fusion Eng. Des. 159 (2020) 111875.
  10. H. Du, Y.-T. Luo, C. Han, L. Lu, Y. Yan, Y. Sun, Y. Chen, S. Liu, Development of an assistant program for CAD-to-cosRMC modelling, Fusion Eng. Des. 157 (2020) 111662.
  11. H. Du, Y.-T. Luo, C. Han, L. Lu, Y. Yan, Y. Sun, Y. Chen, S. Liu, Development of an assistant program for CAD-to-cosRMC modelling, Fusion Eng. Des. 157 (2020) 111662.
  12. C. Yi-xue, W. Yi-can, Effect of fusion neutron source numerical models on neutron wall loading in a DD tokamak device, Plasma Sci. Technol. 5 (2) (2003) 1749.
  13. C. Fausser, A.L. Puma, F. Gabriel, R. Villari, Tokamak DT neutron source models for different plasma physics confinement modes, Fusion Eng. Des. 87 (5-6) (2012) 787-792.
  14. S. Breidokaite, G. Stankunas, Helium production and material damage rate assessment in EU DEMO HCPB divertor, Radiat. Phys. Chem. 210 (2023) 111024.
  15. M. Gilbert, S. Dudarev, S. Zheng, L. Packer, J.-C. Sublet, An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation, Nucl. Fusion 52 (8) (2012) 083019.