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Author : Zdenek Kolarik
Publisher :
ISBN 13 :
Total Pages : 18 pages
Book Rating : 4.:/5 (354 download)
Download or read book Solvent Extraction Recovery of Plutonium from Raffinate Concentrates in the Purex Process written by Zdenek Kolarik and published by . This book was released on 1985 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : E. R. Irish
Publisher :
ISBN 13 :
Total Pages : 72 pages
Book Rating : 4.:/5 (319 download)
Download or read book The Purex Process written by E. R. Irish and published by . This book was released on 1957 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : R. A. Leonard
Publisher :
ISBN 13 :
Total Pages : 88 pages
Book Rating : 4.:/5 (929 download)
Download or read book The Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the Truex Process - Continuing Development Studies written by R. A. Leonard and published by . This book was released on 1985 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : B. F. Judson
Publisher :
ISBN 13 :
Total Pages : 30 pages
Book Rating : 4.3/5 (91 download)
Download or read book Performance of a Plutonium Reflux Solvent Extraction System written by B. F. Judson and published by . This book was released on 1957 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the TRUEX Process - Continuing Development Studies written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report summarizes the work done to date on the application of the TRUEX solvent extraction process for removing and separately recovering plutonium and americium from a nitric acid waste solution containing these elements, uranium, and a complement of inert metal ions. This simulated waste stream is typical of a raffinate from a tributyl phosphate (TBP)-based solvent extraction process for removing uranium and plutonium from dissolved plutonium-containing metallurgical scrap. The TRUEX process solvent in these experiments was a solution of TBP and octyl(phenyl)-N, N-diisobutylcarbamoylmethylphosphine oxide (CMPO) dissolved in carbon tetrachloride. A flowsheet was designed on the basis of measured batch distribution ratios to reduce the TRU content of the solidified raffinate to less than or equal to 10 nCi/g and was tested in a countercurrent experiment performed in a 14-stage Argonne-model centrifugal contractor. The process solvent was recycled without cleanup. An unexpectedly high evaporative loss of CCl4 resulted in concentration of the active extractant, CMPO, to nearly 0.30M in the solvent. Results are consistent with this higher CMPO concentration. The raffinate contained only 2 nCi/g of TRU, but the higher CMPO concentration resulted in reduced effectiveness in the stripping of americium from the solvent. Conditions can be easily adjusted to give high yields and good separation of americium and plutonium. Experimental studies of the hydrolytic and gamma-radiolytic degradation of the TRUEX-CCl4 showed that solvent degradation would be (1) minimal for a year of processing this typical feed, which contained no fission products, and (2) could be explained almost entirely by hydrolytic and radiolytic damage to TBP. Even for gross amounts of solvent damage, scrubbing with aqueous sodium carbonate solution restored the original americium extraction and stripping capability of the solvent. 43 refs., 5 figs., 36 tabs.
Author : Thomas H. Siddall
Publisher :
ISBN 13 :
Total Pages : 20 pages
Book Rating : 4.3/5 (91 download)
Download or read book DI-2-Amyl 2-Butylphosphonate as an Extractant for the Recovery of Uranium and Plutonium written by Thomas H. Siddall and published by . This book was released on 1961 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : E. R. Irish
Publisher :
ISBN 13 :
Total Pages : 18 pages
Book Rating : 4.:/5 (319 download)
Download or read book Description of Purex Plant Process written by E. R. Irish and published by . This book was released on 1959 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Purex process is a continuous solvent extraction process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.
Author :
Publisher :
ISBN 13 :
Total Pages : 24 pages
Book Rating : 4.3/5 (91 download)
Download or read book Recovery of Plutonium from Irradiated Plutonium-aluminum Alloy written by and published by . This book was released on 1962 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Glenn A. Burney
Publisher :
ISBN 13 :
Total Pages : 20 pages
Book Rating : 4.3/5 (91 download)
Download or read book Thermochemical Measurements of Purex Process Solutions written by Glenn A. Burney and published by . This book was released on 1956 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : W. W. Schulz
Publisher :
ISBN 13 :
Total Pages : 52 pages
Book Rating : 4.3/5 (91 download)
Download or read book D2EHPA Extraction Recovery of Neptunium and Plutonium from Purex Acid Sludge Solutions written by W. W. Schulz and published by . This book was released on 1968 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 420 pages
Book Rating : 4.0/5 ( download)
Download or read book Energy Research Abstracts written by and published by . This book was released on 1993 with total page 420 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 7 pages
Book Rating : 4.:/5 (727 download)
Download or read book Recovery of Plutonium from Solvent Wash Solutions written by and published by . This book was released on 1992 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: A number of potential alternatives to the acid hydrolysis recovery of Pu were investigated. The most promising alternative for short-term use appears to be an anion exchange process that would eliminate the long boiling times and the multiple-pass concentration steps needed with the solvent extraction process because it separates the Pu from the dibutyl phosphate (DBP) while at the same time concentrating the Pu. However, restart of the Primary Recovery Column (PRC) to process this solution would require significant administrative effort. The original boiling recovery by acid hydrolysis followed by solvent extraction is probably the most expedient way to process the Pu-DBP-carbonate solution currently stored in tank 13.5 even with its long processing times and dilute product concentration. Anion exchange of a heat stabilized acidified solution is a more efficient process, but requires restart of the PRC. Extended-boiling acid hydrolysis or anion exchange of a heat stabilized acidified solution provide two well developed alternatives for recovery of the Pu from the tank 13.5 carbonate. Further work defining additional recovery processes is not planned at this time.
Author : D. H. Logsdail
Publisher : Ellis Horwood
ISBN 13 :
Total Pages : 234 pages
Book Rating : 4.3/5 (91 download)
Download or read book Solvent Extraction and Ion Exchange in the Nuclear Fuel Cycle written by D. H. Logsdail and published by Ellis Horwood. This book was released on 1985 with total page 234 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book covers most aspects of the processing of these fuels, bringing together the current thinking of international scientists and presenting a picture of the applications of solvent and ion exchange in the fuel cycle.
Download or read book Solvent Extraction and Recovery of the Transuranic Elements from Waste Solutions Using the TRUEX Process written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: High-level liquid waste is produced during the processing of irradiated nuclear fuel by the PUREX process. In some cases the treatment of metallurgical scrap to recover the plutonium values also generates a nitric acid waste solution. Both waste solutions contain sufficient concentrations of transuranic elements (mostly 241Am) to require handling and disposal as a TRU waste. This paper describes a recently developed solvent extraction/recovery process called TRUEX (transuranium extraction) which is designed to reduce the TRU concentration in nitric waste solutions to
Download or read book Purex Process for Plutonium and Uranium Recovery written by and published by . This book was released on 1949 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Labcratory data which indicate that the recovery of Pu and U and decontamination from fission products are feasible in a solvent extraction process using tributyl phosphate are given. The procedure consists of extracting Pu(IV) and U with 15% TBP--85% Varsol using 5.0 N HNO/sub 3/ as a salting agent. (J.R.D.).
Author :
Publisher :
ISBN 13 :
Total Pages : 27 pages
Book Rating : 4.:/5 (684 download)
Download or read book Preliminary Evaluation of Solvent-extraction and written by and published by . This book was released on 2002 with total page 27 pages. Available in PDF, EPUB and Kindle. Book excerpt: Several potential processes are described and evaluated for their suitability in a multitier aqueous-based approach to processing dissolved spent nuclear fuel under the Advanced Accelerator Applications (AAA) program. The evaluation is focused on solvent extraction and ion exchange technologies that have been demonstrated to varying degrees. The goals of the program are to separate uranium (U), technetium (Tc), and the transuranic (TRU) elements from the fission products that are to be vitrified for disposal as high-level waste (HLW). Uranium will be disposed as low-level waste (LLW); Tc and TRU will be transmuted in an accelerator. A number of processes have been examined. The focus was on liquid-liquid solvent extraction processes because of their relatively high state of development and their suitability for high-throughput-rate processing. Ion exchange processes were also examined. PUREX and UREX were evaluated as options for recovery of uranium; UREX is also an option for Tc recovery. Solvent extraction options examined for TRU recovery included TRUEX, DIAMEX, and TRPO, as well as some based on TBP extraction. Processes for trivalent actinide separation from lanthanides were also examined. The PUREX processes have been developed over many years, and have been refined to a significant degree. In the first cycle, U and plutonium (Pu) are co-extracted from dissolved spent fuel solutions by TBP in a diluent, selectively stripped, and purified in additional extraction/strip cycles. Neptunium (Np) can be extracted or driven into the raffinate by adjusting the oxidation state. Trivalent actinides and fission products remain predominantly in the raffinate, although a significant Tc fraction will co-extract with the U and Pu.
Author :
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (893 download)
Download or read book DBBP Solvent Extraction Recovery of Neptunium and Plutonium from Purex 1WW Solution written by and published by . This book was released on 1969 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
