高放废料固化用硼硅酸盐材料研究进展
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摘要
硼硅酸盐固化体是研究最广泛的高放废料固化体,也是高放废料成分的良好溶剂。该体系具有良好的抗辐照性、热稳定性、化学稳定性、耐水性。本文着重从硼硅酸盐玻璃及玻璃陶瓷固化体的固化机理、固化体系及其特点综述其研究和开发进展,并对其今后的发展趋势进行展望。
Borosilicate solidifying agent is the most widely studied high-level waste solidification and is also a good solvent for the high radioactive waste. It has good radiation resistance, thermal stability, chemical durability and water tolerance. In this paper, the embedding mechanism, embedding system and characteristics of the borosilicate glass and the vitreous ceramic embedding body were described, and their research and development progress were also discussed. The development trend of this embedding body was prospected.
Borosilicate solidifying agent is the most widely studied high-level waste solidification and is also a good solvent for the high radioactive waste. It has good radiation resistance, thermal stability, chemical durability and water tolerance. In this paper, the embedding mechanism, embedding system and characteristics of the borosilicate glass and the vitreous ceramic embedding body were described, and their research and development progress were also discussed. The development trend of this embedding body was prospected.
引文
[1]徐凯.核废料玻璃固化国际研究进展[J].中国材料进展,2016,35(7):481-488.
[2]柳伟平,高振,范承蓉,等.法国高放废液玻璃固化技术最新进展[J].辐射防护,2014,34(6):404-406.
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[4]丁新更,李平广,杨辉,等.硼硅酸盐玻璃固化体结构及化学稳定性研究[J].稀有金属材料与工程,2013,42(S1):325-328.
[5]吴浪.高放废液固化处理技术研究新进展[J/OL].科技创新导报,2016,13(5):66-67.
[6]宁海霞,吴浪.钙钛锆石基玻璃陶瓷固化高放废物研究进展[J].材料导报,2015,29(S1):337-340.
[7]李平广.模拟核素的硼硅酸盐玻璃及玻璃陶瓷固化技术研究[D].浙江大学,2013.
[8]王铁山,张多飞,陈亮,等.辐照导致硼硅酸盐玻璃机械性能变化[J].物理学报,2017,66(2):273-280.
[9]Ojovan M I,Lee W E.Preface-An Introduction to Nuclear Waste Immobilisation[J].An Introduction to Nuclear Waste Immobilisation,2005:xvxvi.
[10]李江波,李扬,李宝军,等.掺加铬对硼硅酸盐玻璃固化体结构影响[J].功能材料,2017,48(7):7209-7214.
[11]Cachia J N,Deschanels X,Auwer C D,et al.Enhancing cerium and plutonium solubility by reduction in borosilicate glass[J].Journal of Nuclear Materials,2006,352(13):182-189.
[12]Deschanels X,Peuget S,Cachia J N,et al.Plutonium solubility and self-irradiation effects in borosilicate glass[J].Progress in Nuclear Energy,2007,49(8):623-634.
[13]Stefanovsky S,Shyriaev A,Zubavichus Y V,et al.Plutonium Environment in Lanthanide Borosilicate Glass[J].Mrs Proceedings,2010,1264.
[14]Fox K M,Marra J C,Edwards T B,et al.Plutonium Feed Impurity Testing in Lanthanide Borosilicate(La BS)Glass[J].Mrs Proceedings,2008,1107(1107).
[15]Stefanovsky S V,Shiryaev A A,Vlasova I E,et al.Electron Microscopy and Raman Spectroscopy Study of Pu-Bearing La BS Glasses[J].Mrs Online Proceedings Library Archive,2012,1444.
[16]王欣.含硫钡硼硅酸盐玻璃陶瓷固化体的组成、结构和抗浸出性能的研究[D].西南科技大学,2017.
[17]刘丽君,徐建华,姜耀中.玻璃固化过程中硫酸盐分相和分解行为研究[J].原子能科学技术,2015,49(9):1551-1556.
[18]Jahagirdar P B,Wattal P K.Vitrification of sulphate bearing high level wastes in borosilicate matrix[J].Waste Management,1998,18(4):265-273.
[19]廖其龙,廖春娟,向光华,等.Al O对独居石玻璃陶瓷固2 3化体的影响[J].原子能科学技术,2014,48(1):23-27.
[20]Marra J.Development of an Alternative Glass Formulation for Vitrification of Excess Plutonium[J].Taiwan Pharmaceutical Journal,2006,59(1):105-110.
[21]廖长忠,施凯闵.钙钛锆石基玻璃陶瓷固化锕系核素模拟物的研究[C]//废物地下处置学术研讨会.2014.
[22]吴浪.高放废液固化处理技术研究新进展[J].科技创新导报,2016,13(5):66-67.
[23]Zhang Y,Gregg D J,Kong L,et al.Zirconolite glass-ceramics for plutonium immobilization:The effects of processing redox conditions on charge compensation and durability[J].Journal of Nuclear Materials,2017.
[24]朱鑫璋,罗上庚,汪德熙.锕系核素的人造岩石固化[J].核科学与工程,1997,(2):82-87.
[25]Loiseau P,Caurant D.Glassceramic nuclear waste forms obtained by crystallization of Si O Al O Ca OZr O Ti O,2 2 3 2 2glasses containing lanthanides(Ce,Nd,Eu,Gd,Yb)and actinides(Th):Study of the crystallization from the surface[J].Journal of Nuclear Materials,2010,402(1):38-54.
[26]Vance E R,Ball C J,Day R A,et al.Actinide and rare earth incorporation into zirconolite[J].Journal of Alloys&Compounds,1994,s 213214(1):406-409.
[27]Caurant D,Majerus O,Loiseau P,et al.Crystallization of neodymium-rich phases in silicate glasses developed for nuclear waste immobilization[J].Journal of Nuclear Materials,2006,354(13):143-162.
[28]李鹏,丁新更,杨辉,等.钙钛锆石玻璃陶瓷体的晶化和抗浸出性能[J/OL].硅酸盐学报,2012,40(2):324-328.
[29]陈晓谋,孟成,张峰,等.Ce O掺量对硼硅酸盐玻璃陶瓷固2化体结构的影响[J].稀有金属材料与工程,2016,45(S1):194-197.
[30]吴浪,李会东,肖继宗.钡硼硅酸盐玻璃和玻璃陶瓷固化体的抗浸出性能比较研究[J].科技视界,2016,(18):72-73.
[2]柳伟平,高振,范承蓉,等.法国高放废液玻璃固化技术最新进展[J].辐射防护,2014,34(6):404-406.
[3]卢喜瑞,董发勤.钆锆烧绿石固化锕系核素机x理及稳定性[M].北京:科学出版社,2016.5-8.
[4]丁新更,李平广,杨辉,等.硼硅酸盐玻璃固化体结构及化学稳定性研究[J].稀有金属材料与工程,2013,42(S1):325-328.
[5]吴浪.高放废液固化处理技术研究新进展[J/OL].科技创新导报,2016,13(5):66-67.
[6]宁海霞,吴浪.钙钛锆石基玻璃陶瓷固化高放废物研究进展[J].材料导报,2015,29(S1):337-340.
[7]李平广.模拟核素的硼硅酸盐玻璃及玻璃陶瓷固化技术研究[D].浙江大学,2013.
[8]王铁山,张多飞,陈亮,等.辐照导致硼硅酸盐玻璃机械性能变化[J].物理学报,2017,66(2):273-280.
[9]Ojovan M I,Lee W E.Preface-An Introduction to Nuclear Waste Immobilisation[J].An Introduction to Nuclear Waste Immobilisation,2005:xvxvi.
[10]李江波,李扬,李宝军,等.掺加铬对硼硅酸盐玻璃固化体结构影响[J].功能材料,2017,48(7):7209-7214.
[11]Cachia J N,Deschanels X,Auwer C D,et al.Enhancing cerium and plutonium solubility by reduction in borosilicate glass[J].Journal of Nuclear Materials,2006,352(13):182-189.
[12]Deschanels X,Peuget S,Cachia J N,et al.Plutonium solubility and self-irradiation effects in borosilicate glass[J].Progress in Nuclear Energy,2007,49(8):623-634.
[13]Stefanovsky S,Shyriaev A,Zubavichus Y V,et al.Plutonium Environment in Lanthanide Borosilicate Glass[J].Mrs Proceedings,2010,1264.
[14]Fox K M,Marra J C,Edwards T B,et al.Plutonium Feed Impurity Testing in Lanthanide Borosilicate(La BS)Glass[J].Mrs Proceedings,2008,1107(1107).
[15]Stefanovsky S V,Shiryaev A A,Vlasova I E,et al.Electron Microscopy and Raman Spectroscopy Study of Pu-Bearing La BS Glasses[J].Mrs Online Proceedings Library Archive,2012,1444.
[16]王欣.含硫钡硼硅酸盐玻璃陶瓷固化体的组成、结构和抗浸出性能的研究[D].西南科技大学,2017.
[17]刘丽君,徐建华,姜耀中.玻璃固化过程中硫酸盐分相和分解行为研究[J].原子能科学技术,2015,49(9):1551-1556.
[18]Jahagirdar P B,Wattal P K.Vitrification of sulphate bearing high level wastes in borosilicate matrix[J].Waste Management,1998,18(4):265-273.
[19]廖其龙,廖春娟,向光华,等.Al O对独居石玻璃陶瓷固2 3化体的影响[J].原子能科学技术,2014,48(1):23-27.
[20]Marra J.Development of an Alternative Glass Formulation for Vitrification of Excess Plutonium[J].Taiwan Pharmaceutical Journal,2006,59(1):105-110.
[21]廖长忠,施凯闵.钙钛锆石基玻璃陶瓷固化锕系核素模拟物的研究[C]//废物地下处置学术研讨会.2014.
[22]吴浪.高放废液固化处理技术研究新进展[J].科技创新导报,2016,13(5):66-67.
[23]Zhang Y,Gregg D J,Kong L,et al.Zirconolite glass-ceramics for plutonium immobilization:The effects of processing redox conditions on charge compensation and durability[J].Journal of Nuclear Materials,2017.
[24]朱鑫璋,罗上庚,汪德熙.锕系核素的人造岩石固化[J].核科学与工程,1997,(2):82-87.
[25]Loiseau P,Caurant D.Glassceramic nuclear waste forms obtained by crystallization of Si O Al O Ca OZr O Ti O,2 2 3 2 2glasses containing lanthanides(Ce,Nd,Eu,Gd,Yb)and actinides(Th):Study of the crystallization from the surface[J].Journal of Nuclear Materials,2010,402(1):38-54.
[26]Vance E R,Ball C J,Day R A,et al.Actinide and rare earth incorporation into zirconolite[J].Journal of Alloys&Compounds,1994,s 213214(1):406-409.
[27]Caurant D,Majerus O,Loiseau P,et al.Crystallization of neodymium-rich phases in silicate glasses developed for nuclear waste immobilization[J].Journal of Nuclear Materials,2006,354(13):143-162.
[28]李鹏,丁新更,杨辉,等.钙钛锆石玻璃陶瓷体的晶化和抗浸出性能[J/OL].硅酸盐学报,2012,40(2):324-328.
[29]陈晓谋,孟成,张峰,等.Ce O掺量对硼硅酸盐玻璃陶瓷固2化体结构的影响[J].稀有金属材料与工程,2016,45(S1):194-197.
[30]吴浪,李会东,肖继宗.钡硼硅酸盐玻璃和玻璃陶瓷固化体的抗浸出性能比较研究[J].科技视界,2016,(18):72-73.