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Development of an ion-exchange process for removing cesium from high-level radioactive liquid wastes

Description: Methods to determine resin characteristics, i.e., cesium equilibria and diffusion rates, were developed. These parameters can now guide resin selection and aid in interpreting column performance. The K/sub D/ cesium ion concentration relation gives evidence of three different types of ion exchange sites. The countercurrent load/elution/regeneration cycle for the removal of cesium by ion exchange repeatedly reached the goal decontamination factor (DF) of 10,000 at throughputs up to 60 column volumes. Resin backwashing appears feasible, but further development of column geometry will be required. The proposed ammonium elutriant is satisfactory. Regeneration end-point can be controlled by electrical conductivity monitoring.
Date: November 1, 1979
Creator: Baumgarten, P.K.; Wallace, R.M.; Whitehurst, D.A. & Steed, J.M.
Partner: UNT Libraries Government Documents Department

Plutonium Immobilization Can Loading Equipment Review

Description: This report lists the operations required to complete the Can Loading steps on the Pu Immobilization Plant Flow Sheets and evaluates the equipment options to complete each operation. This report recommends the most appropriate equipment to support Plutonium Immobilization Can Loading operations.
Date: May 1998
Creator: Kriikku, E.; Ward, C.; Stokes, M.; Randall, B.; Steed, J.; Jones, R. et al.
Partner: UNT Libraries Government Documents Department

Preliminary Materials Transport Plan for the Plutonium Immobilization Plant

Description: This Materials Transport Plan defines the methodology for moving process and non-process materials within the Plutonium Immobilization Plant (PIP) operations. The scope of the plan includes the movement of materials between plant operational units (gloveboxes or operational areas/rooms within the plant). The movements of materials within the various plant operational units are described in the System Design Description prepared for the individual units. The plan provides a design concept for transporting each type of material including the containerization used during the movements. Further, the plan identifies the high-level functions and requirements for movements of the materials.
Date: January 26, 2000
Creator: Gilkison, J.M.; Dyches, G.M.; Randall, W.J. & Steed, J.H.
Partner: UNT Libraries Government Documents Department

Plutonium Immobilization Can Loading Concepts

Description: The Plutonium Immobilization Facility will encapsulate plutonium in ceramic pucks and seal the pucks inside welded cans. Remote equipment will place these cans in magazines and the magazines in a Defense Waste Processing Facility (DWPF) canister. The DWPF will fill the canister with glass for permanent storage. This report discusses five can loading conceptual designs and the lists the advantages and disadvantages for each concept. This report identifies loading pucks into cans and backfilling cans with helium as the top priority can loading development areas. The can loading welder and cutter are very similar to the existing Savannah River Site (SRS) FB-Line bagless transfer welder and cutter and thus they are a low priority development item.
Date: May 1998
Creator: Kriikku, E.; Ward, C.; Stokes, M.; Randall, B.; Steed, J.; Jones, R. et al.
Partner: UNT Libraries Government Documents Department