The Advancement of Neutron Shielding Materials for the Storage of Spent Nuclear Fuel

被引:48
作者
Fu, Xuelong [1 ,2 ]
Ji, Zhengbo [1 ]
Lin, Wei [1 ]
Yu, Yunfeng [1 ]
Wu, Tao [1 ]
机构
[1] Jiangsu Vocat & Tech Coll Finance & Econ, Dept Mech & Elect Engn, Huaian 223003, Jiangsu, Peoples R China
[2] Nanjing Univ Aeronaut & Astronaut, Coll Mat Sci & Technol, Nanjing 211106, Peoples R China
关键词
HEAVY-METAL OXIDE; MECHANICAL-PROPERTIES; GAMMA-RAY; CORROSION BEHAVIOR; THERMAL-PROPERTIES; STAINLESS-STEEL; EPDM RUBBER; COMPOSITE; MICROSTRUCTURE; DESIGN;
D O I
10.1155/2021/5541047
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
With the development of nuclear industry, spent nuclear fuel (SNF) generated from nuclear power plants arouses people's attention as a result of its high radioactivity, and how to guarantee the reliable operation of nuclear facilities and the staff's safety occupies a crucial position. To avoid the lethal irradiation, a lot of functional neutron shielding composites have been developed to transform fast neutrons into thermal neutrons which can be absorbed with high macroscopic cross-sectional elements. Irradiation characteristics of nuclear industry have promoted the advancement of neutron shielding materials. Here, we review the latest neutron shielding materials for the storage of spent nuclear fuel containing additives such as boron carbide (B4C), boron nitride (BN), boric acid (H3BO3), and colemanite. Different types of neutron shielding materials, including metal matrix alloys, polymer composites, high density concrete, heavy metals, paraffin, and other neutron shielding composites with high macroscopic cross-sectional elements, arediscussed. The elemental composition, density, and thermal and mechanical properties of neutron shielding materials are also summarized and compared.
引用
收藏
页数:13
相关论文
共 68 条
[31]   Investigation of neutron shielding properties depending on number of boron atoms for colemanite, ulexite and tincal ores by experiments and FLUKA Monte Carlo simulations [J].
Korkut, Turgay ;
Karabulut, Abdulhalik ;
Budak, Gokhan ;
Aygun, Bunyamin ;
Gencel, Osman ;
Hancerliogullari, Aybaba .
APPLIED RADIATION AND ISOTOPES, 2012, 70 (01) :341-345
[32]   Properties of B4C-PbO-Al(OH)3-epoxy nanocomposite prepared by ultrasonic dispersion approach for high temperature neutron shields [J].
Lee, M. K. ;
Lee, J. K. ;
Kim, J. W. ;
Lee, G. J. .
JOURNAL OF NUCLEAR MATERIALS, 2014, 445 (1-3) :63-71
[33]   Effect of mechanical and thermal loading on boron carbide particles reinforced Al-6061 alloy [J].
Manjunatha, B. ;
Niranjan, H. B. ;
Satyanarayana, K. G. .
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2015, 632 :147-155
[34]   Direct reuse of spent nuclear fuel [J].
Mohamed, Nader M. A. .
NUCLEAR ENGINEERING AND DESIGN, 2014, 278 :182-189
[35]   PARAMETERS DETERMINING THE STRENGTH AND TOUGHNESS OF PARTICULATE FILLED EPOXIDE-RESINS [J].
MOLONEY, AC ;
KAUSCH, HH ;
KAISER, T ;
BEER, HR .
JOURNAL OF MATERIALS SCIENCE, 1987, 22 (02) :381-393
[36]   Mechanical Properties and Thermal Neutron Shielding Efficiency of High B Amorphous Ribbons in the Fe-B-Mo-Cr System [J].
Moon, Jaewon ;
Yi, Seonghoon .
METALS AND MATERIALS INTERNATIONAL, 2016, 22 (05) :825-830
[37]   Microstructural characterization and pitting corrosion behavior of UNSS30466 borated stainless steel [J].
Moreno, DA ;
Molina, B ;
Ranninger, C ;
Montero, F ;
Izquierdo, J .
CORROSION, 2004, 60 (06) :573-583
[38]   Development of 300 °C heat resistant boron-loaded resin for neutron shielding [J].
Morioka, Atsuhiko ;
Sakurai, Shinji ;
Okuno, Koichi ;
Sato, Satoshi ;
VerziroV, Yury ;
Kaminaga, Atsushi ;
Nishitani, Takeo ;
Tamal, Hiroshi ;
Kudo, Yusuke ;
Yoshida, Shigeru ;
Matsukawa, Makoto .
JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (1085-1089) :1085-1089
[39]   Thermal and neutron shielding properties of 10B2O3/polyimide hybrid materials [J].
Mulazim, Yusuf ;
Kizilkaya, Canan ;
Kahraman, Memet Vezir .
POLYMER BULLETIN, 2011, 67 (09) :1741-1750
[40]   Polymer-Composite Materials for Radiation Protection [J].
Nambiar, Shruti ;
Yeow, John T. W. .
ACS APPLIED MATERIALS & INTERFACES, 2012, 4 (11) :5717-5726