Dissolution of nuclear fuel

Amme, M. 2002. Contrary effects of the water radiolysis product H2O2 upon the dissolution of nuclear fuel in natural ground water and deionized water. Radiochimica Acta, 90, 399-406. 

Sunder, S., Shoesmith, D. W. Miller, N. H. 1997. Oxidation and dissolution of nuclear fuel (UO2) by the products of the alpha radiolysis of water. Journal of Nuclear Materials, 244, 66-74. 

Figure 7 Electrochemical photothermal deflection spectroscopy experiment (0.5 mol dm-3 Na2S04 pH = 10.5, 20 mV s 1), illustrating the detection of the onset of dissolution of nuclear fuel (U02) (A) voltammetric response for scans to various anodic potential limits (B) and (C) probe beam deflection for each scan. The deflection of the probe beam is proportional to the dissolved uranium concentration, and deflection of the probe beam towards the electrode surface is an indication that dissolution is occurring (Reprinted from Ref. 2 with permission from Elsevier Science S.A.)...

The gaseous radioactive products released by dissolution of nuclear fuel 29jQ(jjne, radioactive aerosols, Krypton, 4c02, Tritium are handled in different ways. Radioactive aerosols are removed by scrubbing and with electrostatic and air filters. absorbed on silver nitrate-... 

A10. Aylward, J. R., and E. M. Whitener Electrolytic Dissolution of Nuclear Fuels, Part II. 

Figure 15 Procedure used to obtain a database of nuclear fuel (U02) corrosion rates (currents) (B) from a Tafel relationship for the anodic dissolution currents for U02 and a series of EC0Rr values measured in radiolytically decomposed solutions (A).

The Fluorinel Dissolution Process Is a specially designed system for processing a number of metal-clad and oxide fuels. A soluble nuclear poison, cadmium, is essential for providing the required production rate and flexibility. Fuel batches are dissolved by (a) removal of the fuel cladding, (b) dissolution of the fuel material, and (c) dissolution of the residual components. Removal of the cladding destroys the fuel element geometry and the fissile material and residual components will 11 to the bottom of the dissolver. The residual components con-... 

Each of these elements may be used for production of nuclear fuel or other purposes. The recovery efficiency for uranium is reported as 99.87% and for plutonium 99.36%-99.51% (NEA 2012). The extended PUREX includes separation of neptunium and technetium as well as recovery of americium and curium that are also separated from each other by additional extraction stages as given in detail in the flowsheet (NEA 2012). The advanced UREX-i-3 process generates six streams after separation uranium for re-enrichment Pu-U-Np for mixed oxide fuel c for managed disposal Am-Cm to be used as burnable poisons and for transmutation high-heat-generating products (Cs and Sr) and a composite vitrified waste with all other fission products. Some fuel types may require preliminary steps like grinding to enable their dissolution. 

The rate of dissolution of these reaction products is slow (1.5-2 fig/day per 50-70 mg of solids). Lai and Goya 147) showed that at least 90% of these plutonium aggregates had a diameter <0.01 jum. However, it must be stressed that these forms do not necessarily represent those forms which would be produced as a result of an accidental release from a nuclear power plant or as a result of controlled release from nuclear fuel reprocessing facilities such as those which occur at Windscale in England. 

Adachi, T., Ohnuki, M. et al. 1990. Dissolution study of spent PWR fuel Dissolution behavior and chemical properties of insoluble residues. Journal of Nuclear Materials, 174, 60-71. 

Gray, W. J., Leider, H. R. Steward, S. A. 1992. Parametric study of LWR spent fuel dissolution kinetics. Journal of Nuclear Materials, 190, 46-52. 

Kleykamp, H. 1990. Post irradiation examinations and composition of the residues from nitric acid dissolution experiments of high bum-up LWR fuel. Journal of Nuclear Materials, 171, 181-188. 

Oversby, V. M. 1999. Uranium Dioxide, SIMFUEL, and Spent Fuel Dissolution Rates - A Review of Published Data. Swedish Nuclear Fuel and Waste Management Co., Stockholm, Sweden, TR-99-22. 

Ahn, T. M. 1996. Long-Term Kinetic Effects and Colloid Formations in Dissolution of LWR Spent Fuels. US Nuclear Regulatory Commission, NUREG-1564. 

Quinones, J., Grambow, B., Loida, A. Geckeis, H. 1996. Coprecipitation phenomena during spent fuel dissolution. Part 1 Experimental procedure and initial results on trivalent ion behavior. Journal of Nuclear Materials, 238, 38-43. 

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