Nuclear fuel, processing

U.S. chlorine trifluoride production is several metric tons per year. Most of the product is used in nuclear fuel processing. A large production plant for chlorine trifluoride was operated in Germany during World War II with a reported capacity of 5 t/d (106,107). As of 1993, Air Products and Chemicals, Inc. was the only U.S. producer. The 1992 price was ca 100/kg. 

J. T. Long, Engineeringfor Nuclear Fuel Processing, American Nuclear Society, LaGrange Park, lU., 1978. 

The simplest dicarboxylate ligand is oxalate, 020 . Thorium oxalate complexes have been used to produce high density fuel pellets, which improve nuclear fuel processes (73). The stabiUty of oxalate complexes and the relevance to waste disposal have also been studied (74). Many thorium oxalate complexes are known, ranging from the simple Th(C20 2 >5rl2 complex salts such as where n = 4, 5, or 6 and where the counterions... 

British Nuclear Fuels PLC, Nuclear Fuel Processing Technology, 1985. 

SREX [Strontium extraction] A process for removing strontium-90 from aqueous wastes from nuclear fuel processing, by solvent extraction into a solution of 18-crown-6 in octanol. Developed by E. P. Horwitz at the Argonne National Laboratory, Chicago, IL, in 1990. 

Another area where titration calorimetry has found intensive application, and where the importance of heat flow versus isoperibol calorimetry has been growing, is the energetics of metal-ligand complexation. Morss, Nash, and Ensor [225], for example, used potenciometric titrations and heat flow isothermal titration calorimetry to study the complexation of UO "1" and trivalent lanthanide cations by tetrahydrofuran-2,3,4,5-tetracarboxylic acid (THFTCA), in aqueous solution. Their general goal was to investigate the potential application of THFTCA for actinide and lanthanide separation, and nuclear fuels processing. The obtained results (table 11.1) indicated that the 1 1 complexes formed in the reaction (M = La, Nd, Eu, Dy, andTm)... 

Actinides occurrence and preparation. With the exception of U and Th, the availability of the actinides of the first half of the series ranges from the g to kg scale that of the elements of the second half of the series from the mg scale for Cf to the sub-mg scale for Es. Isotopes of Np, Pu, Am, Cm can be available as byproducts of nuclear fuel processing other elements such as Ac, Cf, Bk, Es can be obtained by irradiation of selected isotopes in high flux reactors, or by reprocessing large quantities of ore (Pa). 

Schulz, W. Burger, L. L. Navratil, J. D. Eds. Science and Technology of Tributyl Phosphate, Vol. 3, Applications of Tributyl Phosphate in Nuclear Fuel Processing CRC Press Boca Raton, Florida, 1990. 

Kerosene was detected at monitoring wells (concentrations were not reported) located at the perimeter of a spent nuclear fuel processing plant in western New York State in 1983. The kerosene had been used as an extractant during plant operations from 1966 to 1972 (DOE 1989c). 

This process may also be suitable for waste streams from metals reprocessing facilities in addition to those waste streams from nuclear fuels processing and reprocessing facilities. 

Part 1, Fuel Supply (Oct 1973) (PB-235804) Ibid, Part 2, Nuclear Power Reactors (Nov 1973) (PB-235805) Ibid, Part 3, Nuclear Fuel Processing (Dec 1973) (PB-235806) 21) R.H. 

Haller, W.A. Perkins, R.W. (1967) Organic iodine-131 compounds released from a nuclear fuel processing plant. Health Physics, 13, 733-8. 

Gray, L. W., "The Interactions of Hydrazine, Ferrous Sulfa-mate, Sodium Nitrite, and Nitric Acid in Nuclear Fuel Processing Solutions," Nucl. Technol., 1978, 4D (185-193). 

The Applications of Photocatalytic Waste Minimisation in Nuclear Fuel Processing... 

Keywords Actinides Colloidal semiconductor Nuclear fuel processing Photocatalysis Valence control... 

In choosing suitable particulate semiconductor photo catalysts for use in nuclear fuel processing scenarios, it is necessary that certain performance criteria should be fulfilled. Suitable materials should have the following properties ... 

Hydroxamate. Hydroxamate complexes of trivalent actinides can be prepared directly in aqueous solution and other polar solvents and extracted into organic solvents, but due to the high thermodynamic stability of the corresponding tetravalent actinide complexes they are rapidly oxidized. They can also be prepared in solution via electrochemical reduction of the tetravalent complexes. These complexes have been studied for their role in separating high and low valent actinides in nuclear fuel processing schemes. ... 

Hydroxides. Pure and mixed metal actinide hydroxides have been studied for their potential utility in nuclear fuel processing. At the other end of the nuclear cycle, the hydroxides are important in spent fuel aging and dissolution, and environmental contamination. Tetravalent actinides hydrolyze readily, with Th more resistant and Pu more likely to undergo hydrolysis than and Np. All of these ions hydrolyze in a stepwise marmer to yield monomeric products of formula An(OH) with = 1,2,3 and 4, in addition to a number of polymeric species. The most prevalent and well characterized are the mono- and tetra-hydroxides, An(OH) and An(OH)4. Characterization of isolated bis and tri-hydroxides is frustrated by the propensity of hydroxide to bridge actinide centers to yield polymers. For example, for thorium, other hydroxides include the dimers. 

CMPO. CMPO, or octyl(phenyl)-A,A-diisobutylcarbamoylmethylphosphine oxide (see Figure 26), was developed by Horwitz and co-workers as an efficient actinide extractant for use in the TRUEX process in the remediation of acidic nuclear waste solutions. Derivatives of carbamoylphosphine oxides (CMPO) have been studied in nuclear fuel processing schemes involved in transmutation concepts." ... 

Separation of Actinides from High-level Waste (HLW). From the point of view of seeking a possible approach to the ultimate disposal of the HLW from the reprocessing of spent nuclear fuels, processes of solvent extraction and ion-exchange techniques have been studied to recover both americium and lanthanides from the HLW and to separate those subsequently. 

---