Chloride Anion Exchange Coprocessing for Recovery of Plutonium from Pyrochemical Residues and Cs Sub 2 PuCl Sub 6 Filtrate PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Chloride Anion Exchange Coprocessing for Recovery of Plutonium from Pyrochemical Residues and Cs Sub 2 PuCl Sub 6 Filtrate PDF full book. Access full book title Chloride Anion Exchange Coprocessing for Recovery of Plutonium from Pyrochemical Residues and Cs Sub 2 PuCl Sub 6 Filtrate by . Download full books in PDF and EPUB format.
Author: Publisher: ISBN: Category : Languages : en Pages : 19
Book Description
Continuing studies of plutonium recovery from direct oxide reduction (DOR) and electrorefining (ER) pyrochemical process residues show that chloride anion exchange coprocessing is useful and effective. Coprocessing utilizes DOR residue salt as a reagent to supply the bulk of chloride ion needed for the chloride anion exchange process and to improve ER residue salt solubility. ER residue salt and ER scrapeout can be successfully treated, either alone or together, using coprocessing. In addition, chloride anion exchange at 2.0M acidity results in improved process performance by greatly reducing disproportionation of plutonium(IV), eliminating restrictions on oxidation time compared to operation at 1.0M acidity. Laboratory-scale experiments show that below-discard effluent plutonium losses are obtained. Resin capacity was 30 g Pu/l or greater. Furthermore, it is feasible to perform chloride anion exchange recovery of plutonium from filtrate resulting from precipitation of dicesium hexachloroplutonate (Cs2PuCl6, an oxidant salt to be used in the molten salt extraction process) and integration of its preparation with recovery of DOR salts. 10 refs., 9 figs., 10 tabs.
Author: Publisher: ISBN: Category : Languages : en Pages : 19
Book Description
Continuing studies of plutonium recovery from direct oxide reduction (DOR) and electrorefining (ER) pyrochemical process residues show that chloride anion exchange coprocessing is useful and effective. Coprocessing utilizes DOR residue salt as a reagent to supply the bulk of chloride ion needed for the chloride anion exchange process and to improve ER residue salt solubility. ER residue salt and ER scrapeout can be successfully treated, either alone or together, using coprocessing. In addition, chloride anion exchange at 2.0M acidity results in improved process performance by greatly reducing disproportionation of plutonium(IV), eliminating restrictions on oxidation time compared to operation at 1.0M acidity. Laboratory-scale experiments show that below-discard effluent plutonium losses are obtained. Resin capacity was 30 g Pu/l or greater. Furthermore, it is feasible to perform chloride anion exchange recovery of plutonium from filtrate resulting from precipitation of dicesium hexachloroplutonate (Cs2PuCl6, an oxidant salt to be used in the molten salt extraction process) and integration of its preparation with recovery of DOR salts. 10 refs., 9 figs., 10 tabs.
Author: Publisher: ISBN: Category : Ion exchange Languages : en Pages : 84
Book Description
Nine papers are included which were presented at the meeting in Oak Ridge. The papers are chiefly on plutonium separation by anion and cation exchange, although ion exchange contactors, amine extraction of plutonium, and uranium recovery from reduction residues are briefly treated. Separate abstracts have been prepared for each paper. (D.L.C.).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Savannah River Laboratory (SRL), Savannah River Plant (SRP), and Rocky Flats Plant (RFP) are jointly developing a process to recover plutonium from molten salt extraction residues. These NaCl, KCl, MgCl2 residues, which are generated in the pyrochemical extraction of 241Am from aged plutonium metal, contain up to 25 wt % dissolved PUCl3 and up to 2 wt % AmCl3. The objective is to develop a process to convert these residues to plutonium metal product and discardable waste. The first step of the conceptual process is to convert the actinides to a heterogenous scrub alloy with aluminum and magnesium. This step, performed at RFP, effectively separates the actinides from the bulk of the chloride. This scrub alloy will then be dissolved in a HNO3-HF solution at SRP. Residual chloride will be removed by precipitation with Hg2(NO3)2 followed by centrifugation. Plutonium and americium will be separated using the Purex solvent extraction process. The 241Am will be diverted to the solvent extraction waste stream where it can either be discarded to the waste farm or recovered. The plutonium will be finished via PuF3 precipitation, oxidation to a mixture of PUF4 and PuO2, followed by reduction to plutonium metal with calcium.
Author: 
Author: 
Author: A. C. Muscatello
Author: 
Author: Larry Ross Avens
Author: 
Author: W. J. Neill
Author: R. E. Brooksbank
Author: Earl J. Wheelwright
Author: Carl Thomas Bishop
Author: