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Vitrification of ICPP high-level zirconia calcine

Description: High-level radioactive calcined defense waste (approx. 50 wt % CaF/sub 2/) is vitrified using a frit containing 66% SiO/sub 2/, 24% Na/sub 2/O, 8% B/sub 2/O/sub 3/, and 2% CuO. Effects of Na, B, Li, Zn, Cu, and P on viscosity and acid leach resistance were measured. The glass contains up to 9% fluoride. Glass properties were measured.
Date: January 1, 1979
Creator: Berreth, J R; Gombert, D II & Cole, H S
Partner: UNT Libraries Government Documents Department

Microwave energy for post-calcination treatment of high-level nuclear wastes

Description: High-level radioactive wastes generated from nuclear fuel reprocessing require treatment for effective long-term storage. Heating by microwave energy is explored in processing of two possible waste forms: (1) drying of a pelleted form of calcined waste; and (2) vitrification of calcined waste. It is shown that residence times for these processes can be greatly reduced when using microwave energy rather than conventional heating sources, without affecting product properties. Compounds in the waste and in the glass frit additives couple very well with the 2.45 GHz microwave field so that no special microwave absorbers are necessary.
Date: January 1, 1980
Creator: Gombert, D.; Priebe, S.J. & Berreth, J.R.
Partner: UNT Libraries Government Documents Department

An evaluation of neutralization for processing sodium-bearing liquid waste

Description: This report addresses an alternative concept for potentially managing the sodium-bearing liquid waste generated at the Idaho Chemical Processing Plant from the current method of calcining a blend of sodium waste and high-level liquid waste. The concept is based on removing the radioactive components from sodium-bearing waste by neutralization and grouting the resulting low-level waste for on-site near-surface disposal. Solidifying the sodium waste as a remote-handled transuranic waste is not considered to be practical because of excessive costs and inability to dispose of the waste in a timely fashion. Although neutralization can remove most radioactive components to provide feed for a solidified low-level waste, and can reduce liquid inventories four to nine years more rapidly than the current practice of blending sodium-bearing liquid waste with first-cycle raffinite, the alternative will require major new facilities and will generate large volumes of low-level waste. Additional facility and operating costs are estimated to be at least $500 million above the current practice of blending and calcining. On-site, low-level waste disposal may be technically difficult and conflict which national and state policies. Therefore, it is recommended that the current practice of calcining a blend of sodium-bearing liquid waste and high-level liquid waste be continued to minimize overall cost and process complexities. 17 refs., 4 figs., 16 tabs.
Date: January 1, 1989
Creator: Chipman, N.A.; Engelgau, G.O. & Berreth, J.R.
Partner: UNT Libraries Government Documents Department

Post treatment of high-level nuclear fuel wastes

Description: The glass-ceramic product prepared from fluidized-bed calcined synthetic commercial wastes, based on data obtained to date, has many of the properties desired for long-term storage. Although more characterization is necessitated, the product's high-calcine content will decrease the number of storage canisters required and use a minimum of product-forming additives, resulting in significant process cost savings. The product remains in a solid, nonflowing form at temperatures close to the preparation temperature and yet is prepared at relatively low temperatures. The product has void spaces to accommodate radiolytic gas formation, but is hard and dense and has very low leach rates. Process features, such as no direct product contact with furnace or storage canisters, will minimize corrosion of both process equipment and storage canisters. (auth)
Date: January 1, 1975
Creator: Berreth, J.R.; Cole, H.S.; Hoskins, A.P.; Lewis, L.C. & Samsel, E.G.
Partner: UNT Libraries Government Documents Department

Integral capture cross-section measurements in the CFRMF for LMFBR control materials

Description: Integral capture-cross sections for separated isotopes of Eu and Ta are reported for measurements in the Coupled Fast Reactivity Measurements Facility (CFRMF). These cross sections along with that measured in the CFRMF for $sup 10$B(n,$alpha$) provide an absolute standard for evaluating the relative reactivity worth of Eu$sub 2$O$sub 3$, B$sub 4$C and Ta in neutron fields typical of an LMFBR core. Based on these measurements and for neutron fields characterized by the $sup 235$U:$sup 238$U reaction rate spectral index ranging from 23 to 50, the infinitely dilute relative worth of Eu$sub 2$O$sub 3$ has been estimated to be 25 to 40 percent higher than that for B$sub 4$C and 80 percent to 100 percent higher than that for Ta. 11 references. (auth)
Date: January 1, 1975
Creator: Anderl, R.A.; Harker, Y.D.; Turk, E.H.; Nisle, R.G. & Berreth, J.R.
Partner: UNT Libraries Government Documents Department