Encrustation Prevention of Zirconium Molybdate Hydrate

被引:4
作者
Arai, Takahiro [1 ]
Ito, Daiyu [1 ]
Hirasawa, Izumi [1 ]
Miyazaki, Yasunori [2 ]
Takeuchi, Masayuki [2 ]
机构
[1] Waseda Univ, Dept Appl Chem, Grad Sch Adv Sci & Engn, Shinjuku Ku, 3-4-1 Okubo, Tokyo 1698555, Japan
[2] Japan Atom Energy Agcy, Tokai, Ibaraki 3191194, Japan
关键词
Encrustation; Nuclear fuel reprocessing; Reaction crystallization; Relative supersaturation; Zirconium molybdate hydrate; FUEL-REPROCESSING SOLUTIONS; NITRIC-ACID; URANYL-NITRATE; SLUDGE; PRECIPITATION; DISSOLUTION; WASTE;
D O I
10.1002/ceat.201700663
中图分类号
TQ [化学工业];
学科分类号
0817 ;
摘要
In nuclear fuel reprocessing, spent nuclear fuel is dissolved by a nitric acid. It is now known that molybdenum and zirconium in fission products react to form zirconium molybdate hydrate (ZMH). ZMH adheres to the inner surface of reprocessing equipment, which affects the extraction efficiency in the subsequent extraction process. Therefore, a new prevention method of ZMH encrustation is required for stable plant operation. In this study, the encrustation amount of ZMH was investigated. Observing the deposition process, it was clarified that ZMH fine crystals were generated and agglomerated, followed by the rapid deposition. The encrustation amount of ZMH decreased as temperature or initial Mo/Zr mole ratio increased, or as the concentration of a nitric acid was reduced.
引用
收藏
页码:1199 / 1204
页数:6
相关论文
共 24 条
[1]   Characterization of the insoluble sludge from the dissolution of irradiated fast breeder reactor fuel [J].
Aihara, Haruka ;
Arai, Yoichi ;
Shibata, Atsuhiro ;
Nomura, Kazunori ;
Takeuchi, Masayuki .
ATALANTE 2016 INTERNATIONAL CONFERENCE ON NUCLEAR CHEMISTRY FOR SUSTAINABLE FUEL CYCLES, 2016, 21 :279-284
[2]   Performance of inhibitors on CaCO3 scale deposition in stainless steel & copper pipe surface [J].
Al-Roomi, Yousef M. ;
Hussain, Kaneez F. ;
Ai-Rifaie, Mohammed .
DESALINATION, 2015, 375 :138-148
[3]  
[Anonymous], 2001, CRYSTALLIZATION
[4]   Scale formation and control in high pressure membrane water treatment systems: A review [J].
Antony, Alice ;
Low, Jor How ;
Gray, Stephen ;
Childress, Amy E. ;
Le-Clech, Pierre ;
Leslie, Greg .
JOURNAL OF MEMBRANE SCIENCE, 2011, 383 (1-2) :1-16
[5]   PREPARATION AND CRYSTAL-STRUCTURE OF A BASIC ZIRCONIUM MOLYBDATE AND ITS RELATIONSHIP TO ION-EXCHANGE GELS [J].
CLEARFIELD, A ;
BLESSING, RH .
JOURNAL OF INORGANIC & NUCLEAR CHEMISTRY, 1972, 34 (08) :2643-+
[6]   The formation of hydrated zirconium molybdate in simulated spent nuclear fuel reprocessing solutions [J].
Doucet, FJ ;
Goddard, DT ;
Taylor, CM ;
Denniss, IS ;
Hutchison, SM ;
Bryan, ND .
PHYSICAL CHEMISTRY CHEMICAL PHYSICS, 2002, 4 (14) :3491-3499
[7]   Effects of temperature on the scaling of calcium sulphate in pipes [J].
Hoang, Tung A. ;
Ang, H. Ming ;
Rohl, Andrew L. .
POWDER TECHNOLOGY, 2007, 179 (1-2) :31-37
[8]  
Kawamura W., 2000, JP Patent, Patent No. [2000056077A, 2000056077]
[9]   Formation of Molybdenum and Zirconium Precipitates in Concentrated Uranyl Nitrate Solutions [J].
Khonina, I. V. ;
Lumpov, A. A. ;
Shadrin, A. Yu. ;
Zilberman, B. Ya. ;
Kravchenko, N. G. .
RADIOCHEMISTRY, 2010, 52 (02) :175-179
[10]   FORMATION OF PRECIPITATE IN HIGH-LEVEL LIQUID WASTE FROM NUCLEAR-FUEL REPROCESSING [J].
KUBOTA, M ;
FUKASE, T .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1980, 17 (10) :783-790