Abstract
The dissolution behavior of spent fuel with high burn-up was investigated, and the insoluble residues were filtered and analyzed. The dissolution behavior was investigated by tracing the evolution of concentration of U, Pu, Kr and nitric acid. The results showed that UO2 pellets in the irradiated fuel rods sliced to 20–30 mm in length were completely dissolved within 2 h in 6.5 mol/L nitric acid at about 95 °C. The amount and composition of insoluble residues formed in the course of dissolution of spent fuel with the burn-up 40,433 MWd/tU were examined. The weight of the insoluble precipitates was about 2.185 g/kgU. The major elements determining the composition of the precipitates were platinum group metals (Ru, Rh, Pd), Mo and Zr. Depending on the dissolution conditions, the U content was 2.4%, and the Pu content was 0.24% compared to the weight of insoluble residue. The micro-graphs of the residue were observed by SEM.
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References
Ikeda Y, Yasuike Y, Takashima Y, Park YY et al (1993) 17O NMR study on dissolution reaction of UO2 in nitric acid: mechanism of electron transfer. J Nucl Sci Technol 30:962–964
Schwartz S, White W (1981) Solubility equilibrium of the nitrogen oxides and oxy-acids in dilute aqueous solution. Adv Environ Sci Eng 4:1–45
Marc P, Magnaldo A, Vaudano A et al (2017) Dissolution of uranium dioxide in nitric acid media: what do we know? EPJ Nucl Sci Technol 3:1–13
Yasuike Y, Ikeda Y, Kumagai M et al (1991) Kinetic study on dissolution of UO2 powders in nitric acid. RECOD’91 Proc 2:692–697
Hadibi-Olschewski N, Glatz JP, Bokelund H et al (1990) The fate of nitrogen upon reprocessing of nitride fuels. J Nucl Mater 188:244–248
Zhao Y, Chen J (2008) Studies on the dissolution kinetics of ceramic uranium dioxide particles in nitric acid by microwave heating. J Nucl Mater 373:53–58
Claparede L, Tocino F, Szenknect S et al (2015) Dissolution of Th1−xUxO2: effects of chemical composition and microstructure. J Nucl Mater 457:304–316
Desigan N, Augustine E, Murali R (2015) Dissolution kinetics of Indian PHWR natural UO2 fuel pellets in nitric acid: effect of initial acidity and temperature. Prog Nucl Energy 83:52–58
Desigan N, Bhatt N, Pandey NK et al (2015) Mechanism of dissolution of nuclear fuel in nitric acid relevant to nuclear fuel reprocessing. J Radioanal Nucl Chem 312:141–149
Ikeda Y, Yasuike Y, Nishimura K et al (1995) Kinetic study on dissolution of UO2 powders in nitric acid. J Nucl Mater 224:266–272
Fukasawa T, Ozawa Y (1986) Relationship between dissolution rate of uranium dioxide pellets in nitric acid solutions and their porosity. J Radioanal Nucl Chem 106:345–356
Gonda K, Oka K, Nemoto T (1982) Characteristics and behavior of emulsion at nuclear fuel reprocessing. Nucl Technol 57:192–202
Kleykamp H (1985) The chemical state of the fission products in oxide fuels. J Nucl Mater 131:221–246
Gonda K, Oka K, Hayashi K (1984) Nonsoluble fission product residues, crud, and fine chips of zircaloy caldding in headend process of nuclear fuel reprocessing. J Nucl Technol 65:102–108
Adachi T, Ohnuki M, Yoshida N et al (1990) Dissolution study of spent PWR fuel: dissolution behavior and chemical properties of insoluble residue. J Nucl Mater 174:60–71
Kleykamp H, Paschoal JO, Pejsa R et al (1985) Composition and structure of fission product precipitates in irradiated oxide fuels: correlation with phase studies in the Mo–Ru–Rh–Pd and BaO–UO2–ZrO2–MoO2 Systems. J Nucl Mater 130:426–433
Kleykamp H (1987) The composition of residues from the dissolution of irradiated LWR fuels in nitric acid. RECORD-87. In: Proceeding of conference on Paris 23–27 August, vol 2, pp 583–586
Pokhitonov Y, Aleksandruk V, Bibichev B, et al (2002) Composition of insoluble residues generated during spent fuel dissolution. In: WM’02 conference, Tucson, AZ, February 24–28, pp 1–7
Burakova BE, Pokhitonov YA, Ryazantsevb VI et al (2010) Determination of the weight and composition of the precipitates formed in the course of dissolution of irradiated WWER oxide fuel. Radiochemistry 4:403–407
Naito K, Matsui N, Tanaka Y (1986) Recovery of noble metals from insoluble residue of spent Fuel. J Nucl Sci Technol 6:540–549
Li DM, Wang L, Zhang LH et al (2013) Determination of nitric acid in aqueous solution of Uranium and plutonium purification process by near infrared spectroscopy. J Nucl Radiochem 4:96–105 (in Chinese)
Jin HM, Zhu RB, Tan YJ et al (1998) Laboratory studies of hybrid K-edge technology and application (1). Atom Energy Sci Technol 32:193–200 (in Chinese)
Sano Y, Miyachi S, Koizumi T (2005) Dissolution of irradiated MOX fuel for highly concentrated solution. In: Proceedings of GLOBAL 2005. Chiba, Japan, October 9–15, paper 259
Katsurai K, Ohyama K, Kondo Y, et al (2009) Development of highly effective dissolution technology for FBR MOX fuels. In: Proceedings of GLOBAL 2009, Paris, France, September 6–11, paper 9219
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Liu, F., Yan, T.H., Li, B. et al. Dissolution behavior of irradiated fuels in nitric acid and characteristics of insoluble residue. J Radioanal Nucl Chem 326, 337–341 (2020). https://doi.org/10.1007/s10967-020-07350-y
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DOI: https://doi.org/10.1007/s10967-020-07350-y