Design and Mechanical Analysis of Gadolinium-containing Neutron Absorbing Material

被引：0

作者：

Zhang P. ^{[1
]}

Li J. ^{[1
]}

Wang W. ^{[2
]}

Chen H. ^{[2
]}

Xie L. ^{[3
]}

Tan X. ^{[4
]}

机构：

[1] College of Physics and Optoelectronics, Taiyuan University of Technology, Taiyuan

[2] College of Materials Science and Engineering, Taiyuan University of Technology, Taiyuan

[3] Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang

[4] Key Laboratory of Advanced Functional Materials and Devices of Anhui Province, Hefei University of Technology, Hefei

来源：

Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2019年 / 53卷 / 03期

关键词：

Gd[!sub]2[!/sub]O[!sub]3[!/sub; Structure; Tensile property; Thermal neutron;

D O I：

10.7538/yzk.2018.youxian.0703

中图分类号：

学科分类号：

摘要：

A new type of neutron absorbing material with good neutron absorbing capacity, high strength and high toughness was designed to absorb thermal neutron radiation in the nuclear power plant spent fuel storage grid and spent fuel transportation. The material was designed by MCNP which was the Monte Carlo particle transport software, and the plate was prepared by spark plasma sintering equipment and hot rolling. The results of MCNP simulation and thermal neutron absorbing test show that the thermal neutron absorbing performance of Gd2O3/6061Al composite material is comparable to that of B4C/6061Al composite material. After the different ball mill time, the microstructure of Gd2O3 particles is analyzed as micron level, and even some particles reach nanometer scale. The material strength increases with ball mill time. The phase of Gd-Al was detected by X-ray diffraction. The TEM analysis result shows that the strengthening mechanism of the materials is mainly dislocation strengthening and dispersion strengthening of Gd2O3 particle at nanometer level. The tensile strength and elongation reach 240 MPa and 16% respectively, and the fracture is mainly ductile fracture. © 2019, Editorial Board of Atomic Energy Science and Technology. All right reserved.

引用

页码：434 / 441

页数：7

共 19 条

[1] Leake J.W., Lowe T., Mason R.S., Et al., A new method of measuring a large pulsed neutron fluence or dose exploiting the die a way of thermalized neutrons in a polyethylene moderator, Nuclear Instruments and Methods in Physics Research A, 613, 1, pp. 112-118, (2010)
[2] Li Y., Zhang P., Gao Z., Et al., Effect of particle size of B4C reinforcing phase on strength of Al matrix composite plate, Powder Metallurgy Materials Science and Engineering, 17, 5, pp. 611-616, (2012)
[3] Spratt J., Aghara S., Fu B., Et al., A conformal coating for shielding against naturally occurring thermal neutrons, IEEE Transactions on Nuclear Science, 52, 6, pp. 2340-2344, (2005)
[4] Chen H.S., Wang W.X., Nie H.H., Et al., Microstructure evolution and mechanical properties of B4C/6061Al neutron absorber composite sheets fabricated by powder metallurgy, Journal of Alloys and Compounds, 730, pp. 342-351, (2018)
[5] Wu Y., CAD-based interface programs for fusion neutron transport simulation, Fusion Engineering and Design, 4, 7-11, pp. 1987-1992, (2009)
[6] Ozdemir T., Akbay I.K., Uzun H., Et al., Neutron Shielding of EPDM Rubber with Boric Acid: Mechanical, Thermal Properties and Neutron Absorption tests, Progress in Nuclear Energy, 89, pp. 102-109, (2016)
[7] Zhang P., Li Y.L., Wang W.X., Et al., The design, fabrication and properties of B4C/Al neutron absorbers, Journal of Nuclear Materials, 437, 4, pp. 350-358, (2013)
[8] Huang Y., Feng H., Liang L., Et al., Study on absorption and shielding neutron radiation coatings containing B4C, Journal of Tianjin University, 44, 7, pp. 639-644, (2011)
[9] Dai C., Liu X., Liu Z., Monte Carlo simulation of neutron shielding performance of B4C/Al, Acta Physica Sinica, 62, 15, pp. 1-5, (2013)
[10] Aono K., Iwaki M., Namba S., Luminescence during Eu-implantation into calcium fluoride, Nuclear Instruments and Methods in Physics Research B, 32, 14, pp. 231-234, (1988)

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