Author: Keith W. FifePublisher:
ISBN:
Category : Americium
Languages : en
Pages : 29
Book Description
Pyrochemical Investigations Into Recovering Plutonium from Americium Extraction Salt Residues
Author: Keith W. FifePublisher:
ISBN:
Category : Americium
Languages : en
Pages : 29
Book Description
Pyrochemical Investigations Into Recovering Plutonium from Americium Extraction Salt Residues
Author: Keith W. FifePublisher:
ISBN:
Category : Americium
Languages : en
Pages : 0
Book Description
Progress into developing a pyrochemical technique for separating and recovering plutonium from spent americium extraction waste salts has concentrated on selective chemical reduction with lanthanum metal and calcium metal and on the solvent extraction of americium with calcium metal. Both techniques are effective for recovering plutonium from the waste salt, although neither appears suitable as a separation technique for recycling a plutonium stream back to mainline purification processes. 17 refs., 13 figs., 2 tabs.
Recovery of Plutonium from Molten Salt Extraction Residues
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.
Actinide Recovery from Pyrochemical Residues
Author: Larry Ross AvensPublisher:
ISBN:
Category : Actinide elements
Languages : en
Pages : 17
Book Description
Interfacing Solvent Extraction in the Recovery of Pyrochemical Residues at the Savannah River Plant
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The traditional feedstock for plutonium recovery at the Savannah River Plant (SRP) has been spent reactor fuel elements and irradiated targets. Feed sources have included both onsite reactors and a wide variety of domestic and foreign reactors. For the past few years, a growing and increasingly varied mix of unirradiated plutonium residues has been purified through SRP aqueous-based processes. Recently, plutonium residues generated in various chloride salt melts have become a significant offsite source of feed for SRP recovery operations. Impure plutonium metal and plutonium alloys have also been processed. A broader range of molten salt and other high temperature residues is anticipated for the future. The major advantage of solvent extraction for scrap purification is the versatility of the solvent extraction system which allows numerous contaminants to be removed by routine operations. Major concerns are nuclear safety control, corrosion of equipment, and control of releases to the environment. SRP's past, present, and future interfacing of solvent extraction in processing pyrochemical and other plutonium-containing residues is reviewed.
Pyrochemical Processing of Plutonium. Technology Review Report
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Non-aqueous processes are now in routine use for direct conversion of plutonium oxide to metal, molten salt extraction of americium, and purification of impure metals by electrorefining. These processes are carried out at elevated temperatures in either refractory metal crucibles or magnesium-oxide ceramics in batch-mode operation. Direct oxide reduction is performed in units up to 700 gram PuO2 batch size with molten calcium metal as the reductant and calcium chloride as the reaction flux. Americium metal is removed from plutonium metal by salt extraction with molten magnesium chloride. Electrorefining is used to isolate impurities from molten plutonium by molten salt ion transport in a controlled potential oxidation-reduction cell. Such cells can purify five or more kilograms of impure metal per 5-day electrorefining cycle. The product metal obtained is typically> 99.9% pure, starting from impure feeds. Metal scrap and crucible skulls are recovered by hydriding of the metallic residues and recovered either as impure metal or oxide feeds.
Salt Stripping, a Pyrochemical Approach to the Recovery of Plutonium Electrorefining Salt Residues
Author: Dana Carl ChristensenPublisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 29
Book Description
Chloride Anion Exchange Coprocessing for Recovery of Plutonium from Pyrochemical Residues and Cs Sub 2 PuCl Sub 6 Filtrate
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.
Pyrochemistry at Rocky Flats. First Edition
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Pyrochemical and pyrometallurgical processes are utilized at Rocky Flats for plutonium recovery and purification. Many of these processes use molten salts and molten metals which are stirred together or equilibrated at 700 to 900/sup 0/C, resulting in chemical reactions. In one case, an electric current is also applied. These processes include molten salt extraction (MSE) for the removal of americium from plutonium; salt cleanup (SCU) for the recovery of the americium and plutonium from the MSE spent salt; direct oxide reduction (DOR) for the conversion of plutonium oxide to plutonium metal; and two.
Publications of Los Alamos Research
Author: Los Alamos National LaboratoryPublisher:
ISBN:
Category : Research
Languages : en
Pages : 210
Book Description