Nuclear Engineering and Technology

  • 제56권1호
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  • Pages.106-113
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  • 2024
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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In-pile tritium release behavior and the post-irradiation experiments of Li4SiO4 fabricated by melting process

  • Linjie Zhao (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Mao Yang (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Chengjian Xiao (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Yu Gong (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Guangming Ran (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Xiaojun Chen (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Jiamao Li (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Lei Yue (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Chao Chen (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Jingwei Hou (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Heyi Wang (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Xinggui Long (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics) ;
  • Shuming Peng (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics)
  • 투고 : 2023.03.22
  • 심사 : 2023.09.11
  • 발행 : 2024.01.25
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초록

Understanding the tritium release and retention behavior of candidate tritium breeder materials is crucial for breeder blanket design. Recently, a melt spraying process was developed to prepare Li4SiO4 pebbles, which were subsequently subjected to the in-pile tritium production and extraction platform in China Mianyang Research Reactor (CMRR) to investigate their in-situ tritium release behavior and irradiation performance. The results demonstrate that HT is the main tritium release form, and adding hydrogen to the purge gas reduces tritium retention while increasing the HT percent in the purge gas. Post-irradiation experiments reveal that the irradiated pebbles darken in color and their grains swell, but the mechanical properties remain largely unchanged. It is concluded that the tritium residence time of Li4SiO4 made by melt spraying method at 467 ℃ is approximately 23.34 h. High-density Li4SiO4 pebbles exhibit tritium release at relatively low temperatures (<600 ℃) that is mainly controlled by bulk diffusion. The diffusion coefficient at 525 ℃ and 550 ℃ is 1.19 × 10-11 cm2/s and 5.34 × 10-11 cm2/s, respectively, with corresponding tritium residence times of 21.3 hours and 4.7 hours.

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과제정보

This work is supported by the National Key Research and Development Project of China (No.2017YFE0301601), and the National Magnetic Confinement Fusion Science Program (No.2014GB111000).

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