Nuclear fuels based

Several types of nuclear fuels based on uranium or uranium alloys have been fabricated and tested. Among these, uranium-aluminum alloys are probably the most popular, but alloys of uranium with molybdenum (U-Mo), U-Mo-Pt, U-Nb, and U-Mo doped to 1% with several other elements have been tested (Hofman et al. 1998). There are also alloys with U-Zr and U-Si, not to mention mixed oxide fuels like MOX (with plutonium oxide) or uranium with other actinides. 

Other forms of carbon-carbon composites have been or are being developed for space shutde leading edges, nuclear fuel containers for sateUites, aircraft engine adjustable exhaust nozzles, and the main stmcture for the proposed National Aerospace plane (34). For reusable appHcations, a siHcon carbide [409-21 -2] based coating is added to retard oxidation (35,36), with a boron [7440-42-8] h Lsed sublayer to seal any cracks that may form in the coating. 

Other Cell Designs. Although not used in the United States, another important cell is based on designs developed by ICl (90). Cells of this type are used by British Nuclear Fuels pic and differ from the cells shown in Figures 2 and 3 in two ways (/) the anodes used are made of the same hard, nongraphitized carbon, but are more porous and 2) the cathodes are formed from coiled tubes and provide additional cooling (91). 

Includes hydro, nuclear, and geothermal sources, but not fossil fuel-based electricity, which is included in fossil fuels. 

AGNS Staff, Engineering Evaluations of alternativesfor Processing Uranium-Based Fuels, Studies and Research Concerning the Barnwell Nuclear Fuels Plant (BNFP), AGNS-1040-3.1-32, National Technical Information Service (NTlS), Springfield, Va., 1978. 

As previously stated, uranium carbides are used as nuclear fuel (145). Two of the typical reactors fueled by uranium and mixed metal carbides are thermionic, which are continually being developed for space power and propulsion systems, and high temperature gas-cooled reactors (83,146,147). In order to be used as nuclear fuel, carbide microspheres are required. These microspheres have been fabricated by a carbothermic reduction of UO and elemental carbon to form UC (148,149). In addition to these uses, the carbides are also precursors for uranium nitride based fuels. 

U.S. Department of Energy. (1996) Integrated Data Base Report 1995 U.S. Spent Nuclear Fuel and Radioactive Waste Inventories, Projections and Characteristics, DOE/RW-0006, Revision 12. Washington, DC Author. 

Little work has been carried out using electrochemical cells to analyze for impurities. Thermodynamic data have been measured for the interaction of nuclear fuels with liquid potassium using cells based on ThOj-YjOj electrolytes, so such cells could be used to monitor oxygen. Both the diffusion and electrochemical types of hydrogen and carbon meters should function satisfactorily in liquid potassium. 

The development of thorium-based nuclear power cycles still faces various problems and requires much more R D to be commercialised. As a nuclear fuel, thorium could play a more important role in the coming decades, partly as it is more abundant on Earth than uranium and also because mined thorium has the potential to be used completely in nuclear reactors, compared with the 0.7% of natural uranium. Its future use as a nuclear source of energy will, however, depend greatly on the technological developments currently investigated in various parts of the world and the availability of and access to conventional uranium resources. 

High-grade pitchblende ores are leached with nitric acid to recover uranium. Extraction of uranium from nitrate solutions is usually performed with TBP. TBP-based solvents are used in several areas of the nuclear industry, especially for reprocessing of spent nuclear fuels and for refining the uranium product of the Amex and Dapex processes. Extraction of uranium by TBP solvents is described in sections 12.3.4 and 12.5. 

In 1976 he was appointed to Associate Professor for Technical Chemistry at the University Hannover. His research group experimentally investigated the interrelation of adsorption, transfer processes and chemical reaction in bubble columns by means of various model reactions a) the formation of tertiary-butanol from isobutene in the presence of sulphuric acid as a catalyst b) the absorption and interphase mass transfer of CO2 in the presence and absence of the enzyme carboanhydrase c) chlorination of toluene d) Fischer-Tropsch synthesis. Based on these data, the processes were mathematically modelled Fluid dynamic properties in Fischer-Tropsch Slurry Reactors were evaluated and mass transfer limitation of the process was proved. In addition, the solubiHties of oxygen and CO2 in various aqueous solutions and those of chlorine in benzene and toluene were determined. Within the framework of development of a process for reconditioning of nuclear fuel wastes the kinetics of the denitration of efQuents with formic acid was investigated. 

Recent studies on the electrochemical behavior of plutonium in molten salts have mainly been performed in LiCl— KCl based melts. The electrorefining step in a pyroprocessing procedure for the recycling of nuclear fuel from the Integral Fast Reactor (IFR) Program has been... 

MCB MCC MINEQL MOX MSWI p,-SXRF MW Microwave burn-out Materials Characterization Center Mineral equilibria (computer program) Mixed-oxide (fuel) Municipal solid waste incinerator Synchrotron-based X-ray microfluorescence Magnox waste glass (British Nuclear Fuel Public Ltd. Company)... 

These reports are based on 120 technical reports (here denoted by KBS TR) on different technical aspects of waste treatment and ground disposal. More than 70 university departments and consulting companies in Sweden and abroad have been engaged in the preparation of these reports. The research on storage of radioactive waste in the ground is still in progress, both within the Nuclear Fuel Safety Project but also within a Swedish-American joint project between Swedish Nuclear Fuel Supply Co(Svensk Karnbranslefdrsorjning AB, SKBF), Fack, S-10240 Stockholm, Sweden, and Lawrence Berkeley Laboratory, Earth Science Division, University of California, Berkeley. 

Non-carbon-based fuels Nuclear energy Use of nuclear fuels for the production of electric energy used by sectors that require a high intensity... 

Musikas and co-workers studied extensively the extraction behavior of inorganic acids and U/Pu extraction chemistry with A/,A-dialkyl amides (202-205). Based on the extraction data, they proposed certain dialkyl amides suitable for the reprocessing of irradiated nuclear fuels in nitric acid media. Most of the work reported earlier on amides referred to either aromatic or substituted aliphatic hydrocarbons employed as diluents. However, these diluents are not suitable for commercial-scale reprocessing due to their poor radiation and chemical stability in the presence of nitric acid, as well as their tendency to form a three-phase system. 

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