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Nuclear waste materials

Understanding thermo-reaction effects in controlling runaway systems would be applicable toward more efficient and safe harvesting of residual energy from nuclear waste forms. An effort could first be the development of the computational capabilities to simulate the solid-state properties of candidate waste form materials under [Pg.290]

If an effort will focus on Cs and Sr, model equations for the following systems can be derived and simulated  [Pg.291]

their transmuted isobars, in borosilicate glass ceramic [Pg.291]


US DOE 1981. Nuclear Waste Materials Handbook (Test Methods), Report DOE/TIC-11400. DOE Technical Information Center, Washington, DC. [Pg.62]

Buck, E. C., Finn, P. A. Bates, J. K. 2004. Electron energy-loss spectroscopy of anomalous plutonium behavior in nuclear waste materials. Micron, 35, 235-243. [Pg.86]

Oversby, V. M. 1994. Nuclear waste materials. In Frost B. R. T. (ed.) Material science and technology, a comprehensive treatment, Nuclear Materials, VCH, Weinheim, Germany, 10B, 392-442. [Pg.87]

Release rates of radioisotopes should be determined from actual nuclear wastes. The release rates of these isotopes must be measured under conditions of geologic storage. To obtain this data9 Task 2 of the WISAP will study release from waste forms under a variety of conditions to simulate geologic storage of nuclear waste materials. [Pg.90]

The development of solvent-impregnated resins and extraction-chromatographic procedures has enabled the automation of radiochemical separations for analytical radionuclide determinations. These separations provide preconcentration from simple matrices like groundwater and separation from complex matrixes such as dissolved sediments, dissolved spent fuel, or nuclear-waste materials. Most of the published work has been carried out using fluidic systems to couple column-based separations to on-line detection, but robotic methods also appear to be very promising. Many approaches to fluidic automation have been used, from individual FI and SI systems to commercial FI sample-introduction systems for atomic spectroscopies. [Pg.551]

Nuclear Waste Materials Handbook Waste Form Test Methods, MCC-1P Static Test, DOE/TIC-11400, Pacific Northwest Laboratory, Richland, Washington, 1981,... [Pg.359]

In addition to emitting various types of radiation, nuclear waste materials are commonly mixtures of different compounds and even different phases. Energy transfer between phases and interfacial chemistry will affect the yields and types of products formed in these systems. Interfacial effects in radiation chemistry have long been observed, but the detailed mechanisms involved are not understood [3-5], Recent studies of water adsorbed on ceramic oxides clearly show that energy can migrate from the solid oxide phase to the water phase and lead to excess production of H2 [6, 7], This process complicates dosimetry because energy... [Pg.15]

Standard Practice for the Separation of Americium from Plutonium by Ion Exchange Standard Test Method for Pu-238 Isotopic Abundance by Alpha Spectrometry Standard Test Method for Analysis of Aqueous Leachates from Nuclear Waste Materials Using Inductively Coupled Plasma-Atomic Emission Spectrometry... [Pg.412]

Alabama in Mobile, has designed various cations that will attract potentially harmful ions such as mercury, cadmium, uranium, and americium (the latter two are commonly found in nuclear waste materials) and leach them out of contaminated solutions. Davis has also developed cations that will remove HiS (which produces SO2 when the gas is burned) and CO2 (which does not burn) from natural gas. Potentially, these ionic solutions might also be used to remove CO2 from the exhaust gases of fossil-fuel-burning power plants to lessen the greenhouse effect. ... [Pg.857]

The relatively poor ionic conductivity of NaZr2(P04)3 can also be greatly enhanced by substitution of other atoms for the zirconium as, for example, Nai+ r2 Jn (P04)3. Other compounds which have been studied include the series Li,+ Ti2 4.M (P04)3, where M=In, Sc, Cr, Y and Ga, and Nasicon analogues such as Na3M2(P04)3 and Li3M2(P04)3, where M=Cr, Fe, Sc. Many salts with Nasicon or NZP-related structures are now known (Table 12.50) [45-48]. They are possible absorbants for nuclear waste materials. [Pg.1216]

At the back end of the NFC characterization of SNF or nuclear waste materials, focus on the separation and disposal of the radioactive materials—activation products and fission products—formed during irradiation of the fuel. The question of long-term storage of irradiated fuel elements or reprocessing them to separate the useful components (mainly uranium and plutonium) from the hazardous constituents has not yet been settled. [Pg.111]

Mendel, J.E. (1983) Nuclear Waste Materials Handbook of Test Methods, DOE/ TIC-11400, Pacific Northwest Laboratories, Richland, WA, pp. 1-11. [Pg.154]

AG Miller. Laser Raman spectrometric determination of oxy anions in nuclear waste materials. Anal Chem 49 2044-2048, 1977. [Pg.740]

Rare-earth sialon glasses may also have practical applications, for example as fibers for reinforcement, joining agent for ceramics, protective coatings, nuclear waste materials or as seen before, as neutron-absorbent glasses. [Pg.83]

C 1109 Test Method for Analysis of Aqueous Leadiates from Nuclear Waste Materi Using Inductivdy Coupled Plasma-Atomic Emission Spectrometry ... [Pg.800]


See other pages where Nuclear waste materials is mentioned: [Pg.33]    [Pg.84]    [Pg.433]    [Pg.194]    [Pg.17]    [Pg.837]    [Pg.825]    [Pg.146]    [Pg.15]    [Pg.15]    [Pg.882]    [Pg.297]    [Pg.156]    [Pg.663]    [Pg.215]    [Pg.290]    [Pg.477]    [Pg.733]   
See also in sourсe #XX -- [ Pg.290 , Pg.291 , Pg.292 ]




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Nuclear waste

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