Download Chemical Pretreatment of Nuclear Waste for Disposal by Jimmy T. Bell, Luci H. Bell (auth.), Wallace W. Schulz, E. PDF

By Jimmy T. Bell, Luci H. Bell (auth.), Wallace W. Schulz, E. Philip Horwitz (eds.)

Chemical pretreatment of nuclear wastes refers back to the series of separations techniques used to partition such wastes right into a small quantity of high-level waste for deep geologic disposal and a bigger quantity of low-level waste for disposal in a near-surface facility. Pretreatment of nuclear wastes now saved at a number of U. S. division of strength websites levels from easy solid-liquid separations to extra advanced chemical steps, corresponding to dissolution of sludges and removing of chosen radionuclides, e. g. , 90Sr, 99Tc, 137CS, and TRU (transuranium) components. the motive force for improvement of chemical pretreatment methods for nuclear wastes is the commercial good thing about waste minimization as mirrored in decrease charges for near-surface disposal in comparison to the excessive expense of doing away with wastes in a deep geologic repository. This latter topic is expertly and authoritatively mentioned within the introductory paper by means of J. and L. Bell. Seven papers during this quantity describe a number of separations methods constructed or being constructed to pretreat the big quantity of nuclear wastes kept on the US DOE Hanford and Savannah River websites. those papers comprise descriptions of the sort and volume of significant nuclear wastes saved on the Hanford and Savannah River websites in addition to shortly estimated ideas for his or her remedy and ultimate disposal. A paper through Strachan et al. discusses chemical and radiolytic mechanisms for the formation and free up of doubtless explosive hydrogen gasoline in Tank 241-SY-101 on the Hanford site.

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Recently, it has been determined that BPlant will not be used to process Hanford Site tank wastes; rather, a new pretreatment facility will be built. Thus, corrosion of piping in B-Plant become a non-problem. Corrosion should not be a problem in the new facility because appropriate alloys will be chosen for construction of relevant equipment. During the course of many experiments with actual NCRW samples, it was discovered that solids formed in dissolved sludge solutions at sporadic intervals ranging from weeks to days.

90s r) might also need to be removed. Chemical Pretreatment a/Nuclear Waste/or Disposal. W. P. Horwitz, Plenum Press. New Yark, 1995 39 Plutonium Finishing Plant (PFP) sludge,a the critical component is chromium. The next critical component is phosphorus; that is, if the chromium were removed from this sludge, phosphorus would become the limiting component. The third and fourth critical components are sulfur and aluminum, respectively. Removing the critical component results in lowering the number of glass canisters required to dispose of the waste (Table 1).

Buelt, 1989, Process and Facility Options for Pretreatment of Hanford Tank Waste, SD-WM-TA-015, Westinghouse Hanford Company, Richland, Washington. Reilly, S. , C. F. V. Mason, and P. H. Smith, 1992, Cobalt(III) Dicarbollide, A Potential 137Cs and 90Sr Waste Extraction Reagent, U. S. DOE Report LA-11695, Los Alamos National Laboratory, Los Alamos, New Mexico. RHO, 1980a, Technical Status Report on Environmental Aspects of Long-Term Management of High-Level Defense Waste at the Hanford Site, RHO-LD-139, Rockwell Hanford Operations, Richland, Washington.

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