核辐射屏蔽材料研究进展:从传统单一功能到结构功能一体化设计

doi:10.12066/j.issn.1007-2861.2694

摘要/Abstract

摘要： 核能在高速发展的过程中会产生辐射危害,为了保护相关人员的身体健康以及周围环境的安全,必须装备核屏蔽材料.随着辐射防护需求的不断提升,传统单一屏蔽功能材料已无法满足使用需求.开发结构功能一体化且能够应对多种复杂场景的新型核屏蔽材料,并且实现核屏蔽材料的国产化至关重要.简述了新型核屏蔽材料的应用范围及设计要求,概述了目前常见的核屏蔽材料,总结了本课题组近年来开发的多种新型金属基核屏蔽材料.除了作为结构材料外,本课题组开发的核屏蔽材料所具有的中子慢化吸收一体化特性也将成为进一步开发研究的重点.

关键词: 核屏蔽, 中子, $\gamma$射线, 核屏蔽材料

Abstract: Nuclear energy, in the course of its rapid development, also generates radiation hazards. To protect human health and the safety of the surrounding environment, it is necessary to equip nuclear shielding materials. As the demands for radiation protection continue to increase, traditional single-function shielding materials are no longer sufficient. It is essential to develop new-generation nuclear shielding materials that integrate structure and function, capable of addressing various complex scenarios, and to achieve the domestic production of shielding materials. This paper outlines the application range and design requirements for novel nuclear shielding materials, reviews the current mainstream shielding materials, and summarizes various metal-based nuclear shielding materials developed by our research group in recent years. It emphasizes that, in addition to structural applications, the integrated characteristics of neutron moderation and absorption in shielding materials will become a key focus for future research and development.

Key words: nuclear shielding, neutron, gamma-ray, nuclear shielding material

中图分类号:

TG14

潘杰, 刘澳, 王梓榭, 孙泽渊, 李钧, 肖学山. 核辐射屏蔽材料研究进展:从传统单一功能到结构功能一体化设计[J]. 上海大学学报(自然科学版), 2025, 31(5): 757-773.

PAN Jie, LIU Ao, WANG Zixie, SUN Zeyuan, LI Jun, XIAO Xueshan. Research progress on nuclear radiation shielding materials: from traditional single-function to integrated structural and functional design[J]. Journal of Shanghai University（Natural Science Edition）, 2025, 31(5): 757-773.

参考文献

[1] 伍浩松, 孟雨晨. 联合国机构发布碳中和报告呼吁推进核能发展[J]. 国外核新闻, 2022(10): 1-2.
[2] 李奎江, 邹树梁, 唐德文. 核辐射屏蔽材料的研究进展及发展趋势[J]. 现代制造技术与装备, 2017(8): 178-183.
[3] 高静, 丁谦学, 梅其良, 等. 核辐射综合屏蔽材料研究进展[J]. 材料导报, 2023, 37(20): 11-18.
[4] 郑伟, 汤晓斌, 黎俊, 等. 中子/γ射线混合辐射场屏蔽材料研究进展[J]. 宇航总体技术, 2024, 8(6): 66-72.
[5] Natarajan R. Reprocessing of spent nuclear fuel in India: present challenges and future programme [J]. Progress in Nuclear Energy, 2017, 101: 118-132.
[6] Aliyu A S, Evangeliou N, Mousseau T A, et al. An overview of current knowledge concerning the health and environmental consequences of the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident [J]. Environment International, 2015, 85: 213-228.
[7] De La Rosa Blul J C, McMinn P, Grah A. Analysis of the inherent response of nuclear spent fuel pools [J]. Annals of Nuclear Energy, 2019, 124: 295-326.
[8] 黄海, 徐明. 国外可移动式小型核反应堆动力系统的应用研究[J]. 核动力工程, 1995, 16(5): 401-406.
[9] 李晨曦, 伍浩松. 经合组织核能机构发布报告《先进反应堆系统与未来能源市场需求》 [J]. 国外核新闻, 2022(1): 9.
[10] 刘建国. "碳达峰、碳中和" 目标下水运行业低碳发展路径探析[J]. 中国远洋海运, 2021(8): 26-28.
[11] 赵盛, 霍志鹏, 钟国强, 等. 中子及伽马射线复合屏蔽材料的研究进展[J]. 功能材料, 2021, 52(3): 3001-3015.
[12] Wilson J W, Cucinotta F A, Miller J, et al. Approach and issues relating to shield material design to protect astronauts from space radiation [J]. Materials & Design, 2001, 22(7): 541-554.
[13] Grimes S M, Covell T, Jacobs D, et al. High accuracy determination of neutron energies from 300 keV to 5 MeV [J]. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 1995, 99(1): 678-680.
[14] 刘显坤, 刘颖, 唐杰, 等. 高能射线及其屏蔽材料[J]. 核电子学与探测技术, 2006(6): 1034-1038.
[15] More C V, Alsayed Z, Badawi M S, et al. Polymeric composite materials for radiation shielding: a review [J]. Environmental Chemistry Letters, 2021, 19(3): 2057-2090.
[16] 何林, 蔡永军, 李强. 中子和伽马射线综合屏蔽材料研究进展[J]. 材料导报, 2018, 32(7): 1107-1113.
[17] 陈守东, 陈敬超. 铅基核屏蔽材料的研究现状及发展前景展望[J]. 材料导报, 2011, 25(13): 58-60.
[18] 潘晓龙, 张思雨, 郑富凯, 等. 核屏蔽用材料现状及研究进展[J]. 粉末冶金工业, 2022, 32(4): 76-84.
[19] 王玉容, 赵勇, 蒋明忠, 等. 功能/结构一体化中子屏蔽材料的研究现状[J]. 精密成形工程, 2019, 11(3): 166-172.
[20] Mesbahi A, Verdipoor K, Zolfagharpour F, et al. Investigation of fast neutron shielding properties of new polyurethane-based composites loaded with B₄C, BeO, WO₃, ZnO, and Gd₂O₃ micro- and nanoparticles [J]. Polish Journal of Medical Physics and Engineering, 2019, 25(4): 211-219.
[21] Zhang Q P, Liang D M, Zhu W F, et al. Fabrication of h-BN@PbWO₄ with a facile sol-gel method towards enhanced photocatalytic and radiation shielding properties [J]. Journal of Solid State Chemistry, 2019, 269: 594-599.
[22] Fan J H, Wu J Y, Ma Y. Efiect of different size of PbWO₄ particles on EPDM composite for gamma-ray shielding [J]. International Journal of Modern Physics B, 2020, 34(7): 2050046.
[23] Poltabtim W, Thumwong A, Wimolmala E, et al. Dual X-ray- and neutron-shielding properties of Gd₂O₃/NR composites with autonomous self-healing capabilities [J]. Polymers, 2022, 14(21): 4481.
[24] Murari F D, Da Costa E Silva A L V, De Avillez R R. Cold-rolled multiphase boron steels: microstructure and mechanical properties [J]. Journal of Materials Research and Technology, 2015, 4(2): 191-196.
[25] Saghafi M, Ghofrani M B. Accident management support tools in nuclear power plants: a post-Fukushima review [J]. Progress in Nuclear Energy, 2016, 92: 1-14.
[26] Shao Z Z, Wang C L, Song Y T. Structural design and analysis of in wall shielding for ITER [J]. Nuclear Fusion and Plasma Physics, 2011, 31(4): 350-355.
[27] Soliman S, Youchison D, Baratta A, et al. Neutron effects on borated stainless steel [J]. Nuclear Technology, 1991, 96(3): 346-352.
[28] Sorour A A, Chromik R R, Gauvin R, et al. Understanding the solidification and microstructure evolution during CSC-MIG welding of Fe-Cr-B-based alloy [J]. Materials Characterization, 2013, 86: 127-138.
[29] Baron C, Springer H, Raabe D. Development of high modulus steels based on the Fe-Cr-B system [J]. Materials Science and Engineering: A, 2018, 724: 142-147.
[30] He L, Liu Y, Li J, et al. Efiects of hot rolling and titanium content on the microstructure and mechanical properties of high boron Fe-B alloys [J]. Materials & Design, 2012, 36: 88-93.
[31] Liu Y, Li B H, Li J, et al. Efiect of titanium on the ductilization of Fe-B alloys with high boron content [J]. Materials Letters, 2010, 64(11): 1299-1301.
[32] Pan J, Wang Z X, Yang L, et al. Fabrication and characterization of a novel FeCrAl matrix composite containing TiB₂ neutron absorbers synthesized in situ [J]. Materials Characterization, 2021, 181: 111446.
[33] Pan J, Wang C D, Tao Y H, et al. B/Ti atomic ratio and Al content on microstructure and properties of new neutron absorbing austenitic stainless-steel composites [J]. Metallurgical and Materials Transactions A, 2022, 53(10): 3774-3794.
[34] Pan J, Wang C, Zhang H, et al. In situ synthesis and characterization of TiB₂/FeMnAl metal matrix neutron absorption composites [J]. Materials Chemistry and Physics, 2024, 315: 129001.
[35] Wang Q, Li Y, Chen S, et al. Interface alloying design to improve the dispersion of TiB₂ nanoparticles in Al composites: a first-principles study [J]. The Journal of Physical Chemistry C, 2021, 125(10): 5937-5946.
[36] Xu Z G, Jiang L T, Zhang Q, et al. The design of a novel neutron shielding B₄C/Al composite containing Gd [J]. Materials & Design, 2016, 111: 375-381.
[37] Sayyed M I, Mohammed F Q, Mahmoud K A, et al. Evaluation of radiation shielding features of Co and Ni-based superalloys using MCNP-5 code: potential use in nuclear safety [J]. Applied Sciences, 2020, 10(21): 7680.
[38] Lister T E, Pinhero P J, Trowbridge T L, et al. Localized attack of a two-phase metal, scanning electrochemical microscopy studies of NiCrMoGd alloys [J]. Journal of Electroanalytical Chemistry, 2005, 579(2): 291-298.
[39] Zhang C, Pan J, Wang Z X, et al. Gd effect on microstructure and properties of the modifled- 690 alloy for function structure integrated thermal neutron shielding [J]. Nuclear Engineering and Technology, 2023, 55(5): 1541-1558.
[40] Pan J, Wang C, Wang Z, et al. Microstructure characteristics and properties of a novel Nibased alloy for thermal neutron and gamma ray co-shielding [J]. Materials Characterization, 2024, 210: 113840.
[41] Pan J, Ouyang M, Liu A, et al. Corrosion behavior of new nuclear shielding Ni-Cr-W-Gd alloys in simulated spent nuclear fuel pool water [J]. Journal of Materials Research and Technology, 2024, 31: 1200-1214.
[42] Dupont J N, Robino C V, Michael J R, et al. Physical and welding metallurgy of Gdenriched austenitic alloys for spent nuclear fuel applications-part Ⅰ : stainless steel alloys [J]. Welding Journal, 2004, 83(11): 289-300.
[43] Jang J H, Kang J Y, Kim S D. Development of Gd-containing austenitic stainless steel [J]. Journal of Nuclear Materials, 2023, 574: 154197.
[44] Kang J Y, Jang J H, Kim S D, et al. A new type of gadolinium-rich precipitate in alloy steels [J]. Journal of Nuclear Materials, 2020, 542: 152462.
[45] Pan J, Wang Z X, Mei Q L, et al. Control mechanism of gadolinium-rich precipitates in new nuclear shielding FeCrNi alloys [J]. Scripta Materialia, 2023, 234: 115575.
[46] Abenojar J, Velasco F, Martínez M A. Optimization of processing parameters for the Al+10% B₄C system obtained by mechanical alloying [J]. Journal of Materials Processing Technology, 2007, 184(1): 441-446.
[47] Lashgari H R, Emamy M, Razaghian A, et al. The effect of strontium on the microstructure, porosity and tensile properties of A356-10%B₄C cast composite [J]. Materials Science and Engineering: A, 2009, 517(1): 170-179.
[48] 元琳琳, 韩鹏, 陈晓宇, 等. 粉末冶金结合热轧制备高硼铝合金组织与性能研究[J]. 粉末冶金技术, 2018, 36(4): 249-255.
[49] Luan W Z, Jiang C H, Wang H W. Investigation for recrystallization behavior of shot peened layer on TiB₂/6351Al composite using X-ray diffraction [J]. Materials Science and Engineering: A, 2008, 496(1): 36-39.
[50] Wang Z, Pan J, Liu A, et al. Microstructure and properties controlling of Al-xGd alloys for thermal neutron absorbing [J]. Journal of Nuclear Materials, 2025, 603: 155447.
[51] Zhang Q C, Zheng M, Huang Y L, et al. Long term corrosion estimation of carbon steel, titanium and its alloy in backflll material of compacted bentonite for nuclear waste repository [J]. Scientiflc Reports, 2019, 9(1): 3195.
[52] 静永娟, 张继. 热处理对γ-TiAl合金中Gd化合物的影响研究[J]. 金属功能材料, 2013, 20(3): 32-35.
[53] Hur D H, Chun Y B, Park S Y. Corrosion behavior of neutron absorbing Ti-Gd alloys in simulated spent nuclear fuel pool water [J]. Corrosion Science, 2022, 209: 110776.
[54] Kursun C, Gao M, Guclu S, et al. Measurement on the neutron and gamma radiation shielding performance of boron-doped titanium alloy Ti₅₀Cu₃₀Zr₁₅B₅ via arc melting technique [J]. Heliyon, 2023, 9(11): e21696.
[55] Van Houten R. Selected engineering and fabrication aspects of nuclear metal hydrides (Li, Ti, Zr, and Y) [J]. Nuclear Engineering and Design, 1974, 31(3): 434-448.
[56] Sears V F. Neutron scattering lengths and cross sections [J]. Neutron News, 1992, 3(3): 26-37.
[57] Shivprasad A P, Frazer D M, Mehta V K, et al. Elastic moduli of high-density, sintered monoliths of yttrium dihydride [J]. Journal of Alloys and Compounds, 2020, 826: 153955.
[58] Begun G M, Land J F, Bell J T. High temperature equilibrium measurements of the yttriumhydrogen isotope (H2, D2, T2) systems [J]. The Journal of Chemical Physics, 1980, 72(5): 2959- 2966.
[59] Setoyama D, Ito M, Matsunaga J, et al. Mechanical properties of yttrium hydride [J]. Journal of Alloys and Compounds, 2005, 394(1): 207-210.
[60] Hu X, Schappel D, Silva C M, et al. Fabrication of yttrium hydride for high-temperature moderator application [J]. Journal of Nuclear Materials, 2020, 539: 152335.