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JOURNAL OF NUCLEAR MATERIALS · 2025 · IF 3.2

Scalable fabrication and deuterium release properties of Li2TiO3-Li2ZrO3 ceramic pebbles via centrifugal granulation

Guangfan Tan,Qilai Zhou,Yasuhisa Oya,Yingchun Zhang,Chang-An Wang,Yanhao Dong

The Li 2 TiO 3 and Li 2 ZrO 3 ceramic pebbles are regarded as promising tritium breeder on account of their superb chemical stability, high tritium diffusion rates, and neutron multiplication potential of Zr, respectively. To integrate the advantages of these two materials, it is necessary to develop a composite such as Li 2 TiO 3 -Li 2 ZrO 3 , which is ideal for advanced fusion reactor designs. Up to now, fabricated biphasic ceramic pebbles generally suffer from low production yield, inadequate crushing load, and high cost, which restricts their application in practice. In this paper, biphasic Li 2 TiO 3 -Li 2 ZrO 3 tritium breeding pebbles with superior crushing strength are successfully fabricated employing the centrifugal granulation method by selecting the appropriate binder and controlling the growth rate. Moreover, by this technique, ceramic pebbles with wide diameter distribution can be obtained, which will help to improve the packing factor of pebble beds in the solid blanket. In addition, the composition, microstructure, and internal structure of the Li 2 TiO 3 -Li 2 ZrO 3 ceramic pebbles are thoroughly analyzed, respectively. The Li 2 TiO 3 -Li 2 ZrO 3 ceramic pebbles, after being sintered at 1100 °C, attained a high sphericity of 0.97, a superior crushing load of 67.6 N, and an optimum porosity of 9.75 % in the shell. Moreover, the Li 2 TiO 3 -Li 2 ZrO 3 ceramic pebbles also exhibit excellent deuterium release properties with the main form of HDO. The above results show that the centrifugal granulation method is not only applicable to the mass production of Li 2 TiO 3 -Li 2 ZrO 3 ceramic pebbles but also to other tritium breeders, which offers promising prospects for the development of advanced tritium breeding materials in the future.

CAS / MDL: 9004-67-5
研究领域: 材料科学 · 核工程 · 陶瓷学 · 聚变技术
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Materials Today Communications · 2025 · IF 4.5

Microstructure and mechanical property of Y2O3 dispersion-strengthened copper alloy for fusion reactor prepared by spray drying

Hongming Gao,Fufa Wu,Pengfei Zhang,Xiaoyan Zhang,Xingbo Zhang,Hangda Xie,Guodong Sun,Mingyang Li

Y 2 O 3 dispersion-strengthened copper alloy prepared by mechanical alloying (MA) exhibits a high potential to be used as heat-sink materials in the fusion reactor. However, the feasibility of mass-production of the alloy by MA is still suspicious due to the low efficiency and the introduction of impurity elements. In this work, we prepared Y 2 O 3 dispersion-strengthened copper alloy by spray drying, a method suitable for large-scale production with almost no introduction of impurities. Microstructural investigations found that high-density Y 2 O 3 nanoparticles with the size of ∼9 nm are successfully introduced into the copper matrix by spray drying, which greatly refines the grain and inhibits the recrystallization behavior of the alloy. Moreover, most Y 2 O 3 nanoparticles share a coherent interface with the matrix, and as the Y 2 O 3 particles grow, the coherent interfaces transform into semi-coherent interfaces, with an orientation relationship of (11−1) Cu //(422) Y2O3 . The introduction of Y 2 O 3 nanoparticles greatly enhances the strength of the copper matrix by inhibiting the moving of the dislocations and grain boundaries, and a good combination of hardness (114 HV), strength (326.5 MPa), ductility (8.5 %) and electrical conductivity (85.3 %IACS) was achieved in the Cu-2Y 2 O 3 (wt%) alloy. This work proves the feasibility of introducing nano-scale Y 2 O 3 particles into the copper matrix by spray drying, however, the experimental parameters need to be carefully controlled to prevent agglomeration of Y 2 O 3 dispersoids. Large-scale production of ODS-Cu alloys for the fusion reactor may be realized through spray drying in the future.

CAS / MDL: 13494-98-9
研究领域: 材料科学 · 核能工程
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INTERNATIONAL JOURNAL OF HYDROGEN ENERGY · 2023 · IF 7.2

Microfabrication of Li4SiO4 pebbles with complex pore structure via digital light processing: Accuracy control and properties optimizing

Liang Cai,Sirong Tao,Zhen Shen,Li Wan,Ziao Liu,Xilin He,Yingchun Zhang

Li 4 SiO 4 ceramic pebble is deemed as the most attractive tritium breeder for fusion reactor blanket. In this work, we fabricated a novel Li 4 SiO 4 pebble with micrometer-scale pore structure by digital light processing to verify the feasibility of complex pore structure manufacturing for future breeders. The effects of processing parameters on printing accuracy, microstructure and mechanical properties of Li 4 SiO 4 pebbles were investigated. For synthesizing the pure Li 4 SiO 4 phase, the optimal stoichiometric ratio of Li 2 SiO 3 to Li 2 CO 3 was 1:1.09 in the premixed powder. The photosensitivity of dual-phase ceramic suspension was investigated according to an attenuation model, and the overgrowth was reduced to ∼50 μm by using the dimension formula. After optimizing the post-processing, the radial pore structure Li 4 SiO 4 pebbles with excellent crush load (50.3 N, standard deviation = 4.4 N) and suitable open porosity (18.3 %) can be yielded. This work provides a fresh solution to control the pore structure of tritium breeding pebbles in an unprecedented micrometer scale.

研究领域: 材料科学 · 核工程 · 增材制造
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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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JOURNAL OF THE EUROPEAN CERAMIC SOCIETY · 2020 · IF 4.495

Accurate and uniform fabrication of Li2TiO3 pebbles with high properties based on Stereolithography technology

Liang Cai,Xin Hu,Guangfan Tan,Guangbin Li,Yingchun Zhang

Li 2 TiO 3 is a vital candidate breeder to solve tritium self-consistency of fusion reaction. In this study, Digital Light Processing (DLP) based on Stereolithography technology was used to fabricate Li 2 TiO 3 pebbles for the first time. Ceramic suspensions with different solid loadings were prepared by mixing modified Li 2 TiO 3 powder with UV-curable premixture. The size error of Li 2 TiO 3 green pebbles was corrected by adjusting the deformation factor of equatorial radius, and the Li 2 TiO 3 green pebbles were successfully fabricated with an accurate size. After sintering processing, the Li 2 TiO 3 pebbles with a uniform diameter of 1.5 mm and better sphericity of 1.01 were yielded. The sintering behavior of Li 2 TiO 3 pebbles were investigated. Results showed that the Li 2 TiO 3 pebbles formed with 35 vol% solid loading, and sintered at 1050 ℃ had a uniform pore distribution, and also had optimal properties, such as high relative density of 93.6 %TD, and prominent crush load of 92.3 N.

研究领域: 材料科学 · 核工程 · 增材制造
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