典型贵金属元素在玻璃固化体中的溶解度及其对玻璃性质的影响

摘要/Abstract

摘要： 本文主要针对高放废液中贵金属(PGMs)的含量、存在形态,玻璃固化体中PGMs的溶解度、存在形态、颗粒大小等化学行为进行归纳,同时针对玻璃固化过程中PGMs对玻璃性质(流变、粘度、热导、电阻)的影响进行总结。该文为研究典型贵金属元素在玻璃中的溶解度及其变化规律、典型贵金属元素在玻璃中的化学行为及沉淀机理以及典型贵金属元素对玻璃性质的影响研究提供调研基础,可为我国玻璃固化技术的研发提供前期的理论依据。

关键词: 贵金属, 高放废液, 玻璃固化, 溶解度, 玻璃性质

Abstract: This paper mainly summarized the chemical behaviors (the content and the existing form) of precious metals (PGMs) in high-level liquid radioactive waste (HLLW) and the solubility, the existing form and the granularity of PGMs in HLLW glass. At the same time, the influence of PGMs on the properties of HLLW glass (rheology, viscosity, thermal conductivity and resistance) was summarized. The results were expected to provide a research basis for the solubility, the chemical behavior and sediment mechanism of typical PGMs in HLLW glass. Besides, The results were hopeful to provide a theoretical basis for studying the influence of typical PGMs on the properties of HLLW glass.

Key words: precious metal, high-level liquid radioactive waste, vitrification, solubility, properties of glass

中图分类号:

TL941+.113

卢嘉炜, 林鹏, 李丽丽, 赵星, 王怡, 翁汉钦, 林铭章. 典型贵金属元素在玻璃固化体中的溶解度及其对玻璃性质的影响[J]. 辐射防护, 2023, 43(1): 17-30.

LU Jiawei, LIN Peng, LI Lili, ZHAO Xing, WANG Yi, WENG Hanqin, LIN Mingzhang. Solubility of typical PGMs in HLLW glass and influence of PGMs on the properties of HLLW glass[J]. RADIATION PROTECTION, 2023, 43(1): 17-30.

参考文献

[1] Stephane G, Patrick J. Radionuclides containment in nuclear glasses: an overview[J]. Radiochimica Acta, 2017, 105(11): 927-959.
[2] Rahman R, Rakhimov R Z, Rakhimova N R, et al. Cementitious materials for nuclear waste immobilization[M]. United Kingdom: John Wiley Sons, Ltd, 2015.
[3] 罗上庚. 玻璃固化国际现状及发展前景[J]. 硅酸盐通报, 2003, 1: 42-48.
LUO Shanggeng. Status and prospect of vitrification technology [J]. Bulletin of the Chinese Ceramic Society, 2003, 1: 42-48.
[4] 徐凯. 核废料玻璃固化国际研究进展[J]. 中国材料进展, 2016, 35(07): 481-488+517.
XU Kai. Review of international research progress on nuclear waste vitrification[J]. Materials China, 2016, 35(07): 481-488+517.
[5] 卢嘉炜, 郭子方, 吴志豪, 等. 日本高放废液玻璃固化技术[J]. 辐射防护, 2020, 40(01): 67-77.
LU Jiawei, GUO Zifang, WU Zhihao, et al. Vitrification technologies of high level radioactive liquid waste in Japan[J]. Radiation Protection, 2020, 40(01): 67-77.
[6] Sakai A, Koikegami H, Miura N, et al. Development of glass melter technology for HLLW vitrification in Japan[C]// 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014.
[7] Perez J M, Bickford F, Day E, et al. High-level waste melter study report[R]. Office of Scientific & Technical Information Technical Reports, 2001.
[8] Bush R P. Recovery of platinum group metals from high level radioactive waste[J]. Platinum Metals Review, 1991, 35(4): 202-208.
[9] Smith F J, Mcdutfic H F. Recovery of non radioactive palladium and rhodium from radioactive waste[J]. Separation Science & Technology, 1981, 16(9): 1071-1079.
[10] Newman R J, Smith F J. Platinum metals from nuclear fission[J]. Platinum Metals Review, 1970, 14(3): 88-92.
[11] International Atomic Energy Agency. Feasibility of separation and utilization of ruthenium-rhodium and palladium from high level wastes[R]. IAEA, 1989.
[12] Kolarik Z, Renard E V. Potential applications of fission platinoids in industry[J]. Platinur Metals Review, 2005, 49(2): 79-90.
[13] 刘时杰. 一种特殊的铂族金属潜在资源——核废料中的“裂变假铂-FPs[J]. 贵金属, 2013, 34(4): 60-64.
LIU Shijie. An unusual potential resource of platinum group metals——“fission platinoids (FPs)”from nuclear waste materials [J]. Precious Metals, 2013, 34(4): 60-64.
[14] Shimada T, Sawada K, Enokida Y. Effect of dissolving temperature on the amount of palladium dissolved in borosilicate glass[J]. Procedia Chemistry, 2012, 7: 604-609.
[15] 陈松, 管伟明, 张昆华, 等. 核废料中裂变产生的铂族金属(FPs)的开发、应用和发展 [J]. 稀有金属材料与工程, 2007, 36(02): 372-376.
CHEN Song, GUAN Weiming, ZHANG Kunhua, et al. Exploitation, application and development of fission-generated platinum precious metals (FPs) in nuclear waste[J]. Rare Metal Materials & Engineering, 2007, 36(02): 372-376.
[16] Pokhitonov Y A, Estimantovskiy V, Romanovski V, et al. Outlooks of HLW partitioning technologies usage for recovering of platinum metals from spent fuel[R]. Office of Scientific & Technical Information Technical Reports, 2003.
[17] Onishi T, Sekioka K, Suto M, et al. Adsorption of platinum group metals and molybdenum onto aluminum ferrocyanide in spent fuel solution[J]. Energy Procedia, 2017, 131: 151-156.
[18] 杨欣欣. 四种纤维状吸附材料对高放废液中钯离子的吸附行为研究[D]. 武汉工程大学, 2018.
YANG Xinxin. Adsorption behavior of palladium onto four kinds of fibrous adsorbents from simulated high level liquid waste[D]. Wuhan Institute of Technology, 2018.
[19] 顾帅. 裂变产物钯在酸性溶液及其离子液体中的电化学行为研究[D]. 上海交通大学, 2015.
GU Shuai. Electrochemical behavior of fission product palladium in acid and ionic liquid solutions[D]. Shanghai Jiao Tong University, 2015.
[20] 戴安邦. 无机化学教程: 下册[M]. 北京农业大学, 1960: 447-508.
[21] Yamashita M, Yamanaka H, Sasage K I. Dissolution and separation of ruthenium in borosilicate glass[J]. Journal of the American Ceramic Society, 2004, 87(5): 967-969.
[22] Krause C, Luckscheiter B. Properties and behavior of the platinum group metals in the glass resulting from the vitrification of simulated nuclear fuel reprocessing waste[J]. Journal of Materials Research, 1991, 6(12): 2535-2546.
[23] Mukerji J, Biswas S R. Solubility of ruthenium in soda silicate glass[J] .Central Glass & Ceramic Research Institute Bulletin, 1967, 14: 30-34.
[24] Biswas S R, Mukerji J. Solubility of ruthenium in silicate and phosphate glasses[J]. Central Glass & Ceramic Research Institute Bulletin, 1968, 15: 99-103.
[25] Mukerji J, Biswas S R. Oxidation states of ruthenium in glass[J]. Glass Technology, 1971, 12: 107-110.
[26] Schreiber H D, Settle Jr, Jamison P L, et al. Ruthenium in glass forming borosilicate melts[J]. Journal of the Less Common Metals, 1986, 115: 145-154.
[27] Schreiber H D, Harville T R, Damron G N. Redox-controlled solubility of palladium in a borosilicate glass melt[J]. Journal of the American Ceramic Society, 1990.
[28] Yamashita M, Yamanaka H, Sasage K I. Dissolution and separation of ruthenium in borosilicate glass[J]. Journal of the American Ceramic Society, 2004, 87(5): 967-969.
[29] Krause C, Luckscheiter B. Properties and behavior of the platinum group metals in the glass resulting from the vitrification of simulated nuclear fuel reprocessing waste[J]. Journal of Materials Research, 1991, 6(12): 2535-2546.
[30] Mitamura H, Murakami T, Banba T, et al. Segregation of the elements of the platinum group in a simulated high-level waste glass[J]. Nuclear & Chemical Waste Management, 1983, 4(3): 245-251.
[31] Shimada T, Sawada K, Enokida Y. Effect of dissolving temperature on the amount of palladium dissolved in borosilicate glass[J]. Procedia Chemistry, 2012, 7: 604-607.
[32] Akai T, Nishii J, Yamashita M, et al. Chemical behavior of platinum group metals in oxide glasses[J]. Journal of Non Crystalline Solids, 1997, 222: 0-309.
[33] Mitamura H, Murakami T, Banba T. Crystalline phases in a devitrified simulated high level waste glass containing the elements of the platinum group[J]. Journal of Nuclear Mater, 1985, 136: 104-116.
[34] Demin A V, Matyunin Y I, Fedorova M I. Proceedings of the 5th international conference on radioactive waste management and environmental remediation[C]. Berlin, Germany, Vol. 1, ASME, New York, 1995:443.
[35] Mukerji J, Biswas S R. Valency state of ruthenium in glass [J]. Transactions of the Indian, 1969, 28(2): 59-62.
[36] Simonnet C, Grandjean A, Phalippou J. Electrical behavior of platinum group metals in glass forming oxide melts[J]. Journal of Nuclear Materials, 2005, 336(2-3): 243-250.
[37] Hanotin C, Puig J, Neyret M, et al. Platinum group metal particles aggregation in nuclear glass melts under the effect of temperature[J]. Journal of Nuclear Materials, 2016, 477: 102-109.
[38] Luckscheiter B. Proceedings of the 1993 international conference on nuclear waste management and environment remediation[C]. Prague, Czech Republic, 1993:427.
[39] Doubova L M, Daolio S, De Battisti A. Examination of RuO₂ single crystal surfaces: charge storage mechanism in H₂SO₄ aqueous solution[J]. Journal of Electroanalytical Chemistry, 2002, 532: 25-33.
[40] Adachi K, Ishigame J, Sekihara S. Microstmctural glass modifications in as-fired and high-voltage-surged RuO₂-based thick film resistors[J]. Journal of Materials Research, 1991, 6(8): 1729-1735.
[41] Chiang Y M, Silverman L A, French R H, et al. Thin glass film between ultrafine conductor particles in thick-film resistors[J]. Journal of the American Ceramic Society, 1994, 77(5): 1143-1152.
[42] Uruga K, Usami T, Tsukada T, et al. Viscoplasticity of simulated high-level radioactive waste glass containing platinum group metal particles[J]. Journal of Nuclear Materials, 2014, 452(1-3): 419-424.
[43] Boswell G G J, Soentono S. Ruthenium nitrosyl complexes in nitric acid solutions[J]. Journal of Inorganic & Nuclear Chemistry, 1981, 43: 1625-1632.
[44] Brown P G M, Fletcher J M. The significance of certain complexes of ruthenium, niobium, zirconium and uranium in plant processes[J]. Progress in Nuclear Energy, 1961, 3: 120-150.
[45] Scargill D, Lyon C E. Nitratoaquo complexes of nitrosyl ruthenium III[J]. Journal of Inorganic & Nuclear Chemistry, 1965, 27: 161-170.