Reprocessing of nuclear fuels

Neutron-rich lanthanide isotopes occur in the fission of uranium or plutonium and ate separated during the reprocessing of nuclear fuel wastes (see Nuclearreactors). Lanthanide isotopes can be produced by neutron bombardment, by radioactive decay of neighboring atoms, and by nuclear reactions in accelerators where the rate earths ate bombarded with charged particles. The rare-earth content of solid samples can be determined by neutron... 

The breeder reactor, which would produce and bum plutonium and gradually increase the inventory of fissionable material, requires reprocessing of nuclear fuel. As of 1995 only limited research and development was in progress on breeder reactors, mainly in France and Japan. 

As with CIF3, BrF3 is used to fluorinate U to UFe in the processing and reprocessing of nuclear fuel. It is manufactured commercially on a multitonne pa scale and is available as a liquid in steel cylinders of varying size up to 91 kg capacity. The US price in 1992 was 80perkg. 

Figure 31.3 Flow diagram for the reprocessing of nuclear fuel [FP = fission products TBP = (Bu"0)3PO).

The same effect is found also with Pu where the persistence of polymers, even at acidities which would prevent their formation, can cause serious problems in the reprocessing of nuclear fuels. 

As a consequence of the considerable radiotoxicity of these elements there have been very few investigations into the coordination chemistry of the actinides in comparison to other transition elements. The greatest expansion in the coordination chemistry of the actinides might come in the development of new complexing agents which can be used to remove the small quantities of these elements which become contaminants of the human body during the reprocessing of nuclear fuel. 

Ferrous sulfamate [SULFAMIC ACID AND SULFAMATES] (Vol 23) use m chemical reprocessing of nuclear fuel [NUCLEARREACTORS - CHEMICALREPROCESSING] (Vol 17)... 

Wymer, R.G. 1999. Reprocessing of nuclear fuel. In Chemical Separation Technologies and Related Methods ofNuclearWaste Management Application, Problems and Research Needs. Choppin, G.R., Khankhasayev, M.Kh. Eds. Kluwer Academic, Netherlands, pp. 29-52. 

As the focus of this book is on nuclear fuel reprocessing and nuclear-waste cleanup, we will focus on applications in these areas. This section will look at the reprocessing of nuclear fuel and the cleanup and segregation of nuclear waste with SRL and ANL contactors. Finally, other centrifugal contactors used for nuclear processing in France, Japan, Russia, and China will be discussed. 

Chemical resistance to all chemical and radiolytic environments encountered in the reprocessing of nuclear fuels, most especially aqueous environments of high acidity (pH< 2) ... 

The U02+ disproportionates to form U4+ and U022+ while the nitrous acid oxidises further U(IV), although with a higher rate than nitric acid. It would therefore be desirable to provide an alternative process for controlling the oxidation states of U in the reprocessing of nuclear fuel, preferably by the generation of U(IV). 

C1F3 and BrF3 are both used to fluorinate uranium to produce UF6 in the processing and reprocessing of nuclear fuel. Draw Lewis structures for C1F3 and BrF3. 

Reprocessing of nuclear fuel by the Purex process leads to the following amounts of waste per ton of U 1 m HLW (fission products and actinides in HNO3 solution), 3 m MLW as organic solution, 17m MLW as aqueous solution, 90m LLW (aqueous solution). By further processing a volume reduction is achieved 0.1m HLW, 0.2m MLW (organic), 8m MLW (aqueous), 3m LLW (aqueous). 

Actinide separation techniques and methods play a very important role in analysis and production of nuclear materials, reprocessing of nuclear fuels, nuclear waste management, and other aspects of the nuclear fuel cycle. Professionals from several disciplines—analytical chemists, chemical engineers, process chemists, etc.—make much use of this technology. 

Steunenberg, R. K. Pierce, R. D. Johnson, I., "Status of the Salt Transport Process for Fast Breeder Reactor Fuels," in "Symposium on Reprocessing of Nuclear Fuels, The Metallurgical Society of AIME, Ames, IA, August 1969," Nucl. Metallurgy,... 

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