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Initial investigation of B4C-TiB2 composites as neutron absorption material for nuclear reactors

文献类型：期刊论文

作者Wang, Ji4; Ren, Donglou3; Chen, LeiLei2; Man, Guian1; Zhang, Houyuan1; Zhang, Hongpeng5; Luo, Laihui4; Li, Weiping4; Pan, Yanbo4; Gao, Peifeng1
刊名JOURNAL OF NUCLEAR MATERIALS
出版日期2020-10-01
卷号539页码:9
ISSN号0022-3115
关键词Neutron absorber B4C pellet He irradiation Crack propagation Finite element
DOI10.1016/j.jnucmat.2020.152275
通讯作者Gao, Peifeng(gaopf@lzu.edu.cn) ; Zhu, Yabin(zhuyabin@impcas.ac.cn) ; Wang, Zhiguang(zhgwang@impcas.ac.cn)
英文摘要In this study, a specifically designed B4C-TiB2 composite with the typical microstructural feature of a TiB2 network (cages) that encapsulates a B4C matrix was fabricated by the molten-salt and spark plasma sintering (SPS) method. The finite-element (FE) calculation results show that the connected TiB2 cages constitute a thermally conductive network, which effectively improves the overall thermal conductivity of the composite; these results agree well with the experimental results. Moreover, the Vickers indentation results reveal that the TiB2 network (cages) can effectively impinge/block the propagation of cracks, which increases the composite toughness. The composite was subjected to helium (He) ion irradiation to simulate the situation in which the B4C-TiB2 composites serve as neutron absorption material, and for which case a high quantity of He atoms is produced by the B-10(n, alpha)Li-7 nuclear reaction. According to the transmission electron microscopy (TEM) results, the interfaces between TiB2 and B4C act as effective sinks for He atoms, and are preferential nucleation sites for He bubbles. The theoretical and experimental results show that when the B4C-TiB2 composites serve as neutron absorption pellets in nuclear reactors, they exhibit a better resistance to their disintegration than pure B4C pellets. Consequently, the performance of the control rods of nuclear reactors can be improved. (C) 2020 Elsevier B.V. All rights reserved.
WOS关键词BORON-CARBIDE ; CRACK-PROPAGATION ; HELIUM ; DAMAGE ; MICROSTRUCTURE ; IRRADIATION ; STRENGTH ; BEHAVIOR
资助项目National Natural Science Foundation of China[11902129] ; National Natural Science Foundation of China[11805245] ; Strategic Priority Research Program of Chinese Academy of Sciences[XDA21010202] ; Natural Science Fund of Zhejiang Province[LQ20A050001] ; Natural Science Fund of Ningbo City[2019A610183] ; China Postdoctoral Science Foundation[2019T120963]
WOS研究方向Materials Science ; Nuclear Science & Technology
语种英语
出版者ELSEVIER
WOS记录号WOS:000562377500002
资助机构National Natural Science Foundation of China ; Strategic Priority Research Program of Chinese Academy of Sciences ; Natural Science Fund of Zhejiang Province ; Natural Science Fund of Ningbo City ; China Postdoctoral Science Foundation
源URL[http://119.78.100.186/handle/113462/139872]  
专题中国科学院近代物理研究所
通讯作者Gao, Peifeng; Zhu, Yabin; Wang, Zhiguang
作者单位1.Lanzhou Univ, Coll Civil Engn & Mech, Key Lab Mech Western Disaster & Environm, Minist Educ, Lanzhou 730000, Peoples R China
2.Chinese Acad Sci, Ningbo Inst Mat Technol & Engn, Ningbo 315201, Peoples R China
3.Univ Rennes, ISCR Inst Sci Chim Rennes, CNRS, UMR 6226, F-35000 Rennes, France
4.Ningbo Univ, Sch Phys Sci & Technol, Ningbo 315211, Peoples R China
5.Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China
推荐引用方式
GB/T 7714		 Wang, Ji,Ren, Donglou,Chen, LeiLei,et al. Initial investigation of B4C-TiB2 composites as neutron absorption material for nuclear reactors[J]. JOURNAL OF NUCLEAR MATERIALS,2020,539:9.
APA Wang, Ji.,Ren, Donglou.,Chen, LeiLei.,Man, Guian.,Zhang, Houyuan.,...&Wang, Zhiguang.(2020).Initial investigation of B4C-TiB2 composites as neutron absorption material for nuclear reactors.JOURNAL OF NUCLEAR MATERIALS,539,9.
MLA Wang, Ji,et al."Initial investigation of B4C-TiB2 composites as neutron absorption material for nuclear reactors".JOURNAL OF NUCLEAR MATERIALS 539(2020):9.

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来源：近代物理研究所

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