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Nanoscience and Nanotechnology Letters · 2019 ·Vol. 11 ·期 8 ·1173-1177 · IF 0

Secondary Effect of Nitrogen on Hydrogen Isotopes Retention in Tungsten Dust from Fusion Reactor Simulated by Wire Electrical Explosion

Wang Jingchuan,Yao Yong,Luo Junhong,Yao Weizhi,Gao Bo,Chen Chang'an

Nitrogen is potentially used in tokamak as seed impurity for avoiding divertor damage and achieving good plasma performance. Herein, the secondary effect of nitrogen was studied by wire electrical explosion (WEE) method. In the presence of nitrogen, the inventory of hydrogen retention in the tungsten dust was largely increased, while hydrogen was retained by chemical bonding with nitrogen, besides dissolving into lattice and trapping in defects of tungsten, which was identified by FTIR and XRD. This study indicates that nitrogen seed impurity will cause serious tritium retention and speed tungsten-based plasma facing components (PFC)' erosion.

研究领域: 核聚变 · 材料科学 · 等离子体物理

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Nuclear Engineering and Technology · 2023 · IF 2.7

In-pile tritium release behavior and the post-irradiation experiments of Li4SiO4 fabricated by melting process

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

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 Li 4 SiO 4 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 Li 4 SiO 4 made by melt spraying method at 467 °C is approximately 23.34 h. High-density Li 4 SiO 4 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 cm 2 /s and 5.34 × 10 −11 cm 2 /s, respectively, with corresponding tritium residence times of 21.3 hours and 4.7 hours.

CAS / MDL: 1310-66-3

研究领域: 核工程 · 材料科学 · 辐射物理

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Secondary Effect of Nitrogen on Hydrogen Isotopes Retention in Tungsten Dust from Fusion Reactor Simulated by Wire Electrical Explosion

In-pile tritium release behavior and the post-irradiation experiments of Li4SiO4 fabricated by melting process