In-pile tritium release behavior and the post-irradiation experiments of Li4SiO4 fabricated by melting process
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 platfo...
| Main Authors: | , , , , , , , , , , , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2024-01-01
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| Series: | Nuclear Engineering and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573323004230 |
| _version_ | 1797355267755606016 |
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| author | Linjie Zhao Mao Yang Chengjian Xiao Yu Gong Guangming Ran Xiaojun Chen Jiamao Li Lei Yue Chao Chen Jingwei Hou Heyi Wang Xinggui Long Shuming Peng |
| author_facet | Linjie Zhao Mao Yang Chengjian Xiao Yu Gong Guangming Ran Xiaojun Chen Jiamao Li Lei Yue Chao Chen Jingwei Hou Heyi Wang Xinggui Long Shuming Peng |
| author_sort | Linjie Zhao |
| collection | DOAJ |
| description | 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 °C is approximately 23.34 h. High-density Li4SiO4 pebbles exhibit tritium release at relatively low temperatures (＜600 °C) that is mainly controlled by bulk diffusion. The diffusion coefficient at 525 °C and 550 °C 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. |
| first_indexed | 2024-03-08T14:08:42Z |
| format | Article |
| id | doaj.art-1eeac21785e6499ebf4982f3b48bb3fd |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-03-08T14:08:42Z |
| publishDate | 2024-01-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-1eeac21785e6499ebf4982f3b48bb3fd2024-01-15T04:20:45ZengElsevierNuclear Engineering and Technology1738-57332024-01-01561106113In-pile tritium release behavior and the post-irradiation experiments of Li4SiO4 fabricated by melting processLinjie Zhao0Mao Yang1Chengjian Xiao2Yu Gong3Guangming Ran4Xiaojun Chen5Jiamao Li6Lei Yue7Chao Chen8Jingwei Hou9Heyi Wang10Xinggui Long11Shuming Peng12Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, ChinaCorresponding author.; Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, ChinaCorresponding author.; Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, 621900, ChinaUnderstanding 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 °C is approximately 23.34 h. High-density Li4SiO4 pebbles exhibit tritium release at relatively low temperatures (＜600 °C) that is mainly controlled by bulk diffusion. The diffusion coefficient at 525 °C and 550 °C 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.http://www.sciencedirect.com/science/article/pii/S1738573323004230Li4SiO4Melt spraying processIn-situ tritium release behaviorPost-irradiation experiments |
| spellingShingle | Linjie Zhao Mao Yang Chengjian Xiao Yu Gong Guangming Ran Xiaojun Chen Jiamao Li Lei Yue Chao Chen Jingwei Hou Heyi Wang Xinggui Long Shuming Peng In-pile tritium release behavior and the post-irradiation experiments of Li4SiO4 fabricated by melting process Nuclear Engineering and Technology Li4SiO4 Melt spraying process In-situ tritium release behavior Post-irradiation experiments |
| title | In-pile tritium release behavior and the post-irradiation experiments of Li4SiO4 fabricated by melting process |
| title_full | In-pile tritium release behavior and the post-irradiation experiments of Li4SiO4 fabricated by melting process |
| title_fullStr | In-pile tritium release behavior and the post-irradiation experiments of Li4SiO4 fabricated by melting process |
| title_full_unstemmed | In-pile tritium release behavior and the post-irradiation experiments of Li4SiO4 fabricated by melting process |
| title_short | In-pile tritium release behavior and the post-irradiation experiments of Li4SiO4 fabricated by melting process |
| title_sort | in pile tritium release behavior and the post irradiation experiments of li4sio4 fabricated by melting process |
| topic | Li4SiO4 Melt spraying process In-situ tritium release behavior Post-irradiation experiments |
| url | http://www.sciencedirect.com/science/article/pii/S1738573323004230 |
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