Waste Management

Download Ion Exchange and Solvent Extraction: A Series of Advances, by Bruce A. Moyer PDF

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By Bruce A. Moyer

The expansion within the world’s nuclear undefined, stimulated through peaking international oil offers, matters in regards to the greenhouse impact, and household wishes for power independence, has ended in a heightened concentrate on the necessity for next-generation nuclear fuel-cycle applied sciences. Ion alternate and Solvent Extraction: a sequence of Advances, quantity 19 presents a complete examine the country of the technology underlying solvent extraction in its function because the strongest separation process for the reprocessing of industrial spent nuclear gas. taking pictures the present expertise and clinical growth because it exists at the present time and looking out forward to power advancements, the booklet examines the final nation of solvent extraction in reprocessing, new molecules for elevated selectivity and function, equipment for predicting extractant houses, and actinide-lanthanide staff separation. The participants additionally discover the simultaneous extraction of radionuclides by way of blending extractants, the reason and nature of third-phase formation, the results of radiation at the solvent and its functionality, analytical thoughts for measuring approach concentrations, new centrifugal contactors for extra effective processing, and new chemistry utilizing novel media. The long term imaginative and prescient of many execs within the box includes a proliferation-free nuclear strength economic system during which very little waste is saved or published into the surroundings and all capability strength values in spent nuclear gas are recycled. this article opens a window on that risk, delivering perception from international leaders at the leading edge of nuclear learn.

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Extra info for Ion Exchange and Solvent Extraction: A Series of Advances, Volume 19 (Ion Exchange and Solvent Extraction Series) (Vol. 19)

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The knowledge bases are, for example, OECD/NEA’s Thermochemical Database (127, 128), solvent-extraction database and programs for analysis (129–132). Although methodologies of modeling, how to use the tools, depend heavily on the researcher’s expertise, requisite criteria for design is the knowledge about the relationship between ligand structure and the nature of metal-donor group interactions; ­quantitative ­structure-activity relationship (QSAR). Many investigations to establish methodologies for designing ligands possessing high affinity and selectivity to specified metal ions have appeared during the past decade (133–150).

In the framework of the AFCI program, Peterman et al. of Idaho National Laboratory (INL) have examined the feasibility of using the Cyanex 301 system for treating an ammonium acetate/acetic acid buffered solution (308), which was used in the TRUEX process as a strip solution of Ans and Lns. 37 M TBP in n-dodecane was studied. At a region of specific pH value, the intergroup separation of Am + Cm and Lns was concluded to be possible, and it was claimed that a method for removal of degradation products is needed in order to develop a viable large-scale Cyanex 301 process.

J. 2007. Lab-scale demonstration of the UREX+1a process using spent fuel. Proceedings of WM’07, Tucson, AZ, February 25 to March 1. Note: S: storage. T: transmute by thermal (therm) or fast (fast) neutrons. F. Ans: fissile actinides. ASTM C788-98: Standard specification for nuclear-grade uranyl nitrate solution or crystals. ASTM C833-01: Standard specification for sintered (uranium-plutonium) dioxide pellets. 1 Molecular Modeling Approach Molecular design has enjoyed a long history, from the preliminary “trial-and-error” stage to the contemporary computer-aided “molecular modeling” stage.

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