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Download or read book Dissolution of U-Mo-Alloy Scrap from Fuel Fabrication written by and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : J. Vincent Panesko
Publisher :
ISBN 13 :
Total Pages : 18 pages
Book Rating : 4.3/5 (91 download)
Download or read book Selective Dissolution of Uranium from Fuel Fabrication Scrap written by J. Vincent Panesko and published by . This book was released on 1972 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : L. M. Ferris
Publisher :
ISBN 13 :
Total Pages : 44 pages
Book Rating : 4.3/5 (91 download)
Download or read book Aqueous Processes for Dissolution of Uranium-molybdenum Alloy Reactor Fuel Elements written by L. M. Ferris and published by . This book was released on 1961 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : W. W. Schulz
Publisher :
ISBN 13 :
Total Pages : 42 pages
Book Rating : 4.3/5 (91 download)
Download or read book Reprocessing Uranium-molybdenum Alloy Fuels written by W. W. Schulz and published by . This book was released on 1960 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book AQUEOUS PROCESSES FOR DISSOLUTION OF URANIUM-MOLYBDENUM ALLOY REACTOR FUEL ELEMENTS. written by and published by . This book was released on 1961 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Methods for dissolving unirradiated uranium-molybdenum alloy reactcr fuels in nitric acid, nitric acid--ferric nitrate, and nitric acid-- phosphoric acid solutions were studied on a laboratory scale. Flowsheets based on the results propose dissolution of alloys containing 3% molybdenum in boiling 6 M HNO/ sub 3/ to yield stsble solutions that are 0.6 M in uranium and 3 to 4 M in nitric acid. The uranium can then be easily decontaminated and recovered in a conventional Purex-type tributyl phosphate solvent extraction process. Alloys containing 10% molybdenum would be dissolved in boiling 11 M HNO3, allowing molybdic oxide to precipitate. The molybdic oxide, which carries 5-10% of the uranium, is removed by centrifugation and the acidity of the supernatant solution adjusted tc allow recovery of the uranium by Purex-type solvent extraction procedures. The uranium carried by the molybdic oxide is recovered after the MoO/ sub 3/ is dissolved in warm 5 M NaOH. Less than 0.1% of the uranium is solubilized during the caustic dissolution. Alternative methods investigated involve dissolution in nitric acid containing 0.5 to 1 M ferric nitrate to complex the molybdenum. These techniques lead to undesirably large volumes of high-level solvent extraction waste solutions. Phosphate ion is also effective in complexing molybdenum; however, its use in the dissolvent would be purposeless since it must be complexed with iron during solvent extraction. Rates of reaction of the various alloys and the solubility of molybdic oxide were determined in nitric acid, nitric acid-- ferric nitrate, and nitric acid-- phosphonic acid solutions. (auth).
Author : Atomic Industrial Forum
Publisher :
ISBN 13 :
Total Pages : 204 pages
Book Rating : 4.3/5 (91 download)
Download or read book Uranium and the Atomic Industry written by Atomic Industrial Forum and published by . This book was released on 1956 with total page 204 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 160 pages
Book Rating : 4.3/5 (91 download)
Download or read book Nuclear Materials Management written by and published by . This book was released on 1965 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Atomic Industrial Forum
Publisher :
ISBN 13 :
Total Pages : 204 pages
Book Rating : 4.X/5 (4 download)
Download or read book Forum Report written by Atomic Industrial Forum and published by . This book was released on 1956 with total page 204 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book REPROCESSING URANIUM-MOLYBDENUM ALLOY FUELS-DISSOLUTION IN CONCENTRATED NITRIC ACID. written by and published by . This book was released on 1960 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Dissolution of U--3 wt.% Mo alloys in 12 to 14 M HNO3 solutions is discussed. Under these conditions 80 to 95% of the molybdenum content is precipitated as white hydrated molybdic oxide. Molybdic oxide precipitates are bulky; centrifuged volumes range from 6 to 17 vol.% for dissolver solutions 1.0 to 1.5:(M U. The precipitates retain some plutonium and uranium even after thorough washing with water and 1 M HNO3. Plutonium and uranium values in washed precipitates can be recovered by successive treatment of solid residues with caustic and nitric acid. Removal of nitric acid from uranium-molybdenum alloy dissolver solutions by boil-down procedures and by reaction with formaldehyde is discussed. Solutions obtained after removal of nitric acid constitute satisfactory low-acid Redox process feedstocks. (auth).
Author :
Publisher : ScholarlyEditions
ISBN 13 : 1481681435
Total Pages : 219 pages
Book Rating : 4.4/5 (816 download)
Download or read book Actinoid Series Elements—Advances in Research and Application: 2013 Edition written by and published by ScholarlyEditions. This book was released on 2013-06-21 with total page 219 pages. Available in PDF, EPUB and Kindle. Book excerpt: Actinoid Series Elements—Advances in Research and Application: 2013 Edition is a ScholarlyEditions™ book that delivers timely, authoritative, and comprehensive information about Uranium. The editors have built Actinoid Series Elements—Advances in Research and Application: 2013 Edition on the vast information databases of ScholarlyNews.™ You can expect the information about Uranium in this book to be deeper than what you can access anywhere else, as well as consistently reliable, authoritative, informed, and relevant. The content of Actinoid Series Elements—Advances in Research and Application: 2013 Edition has been produced by the world’s leading scientists, engineers, analysts, research institutions, and companies. All of the content is from peer-reviewed sources, and all of it is written, assembled, and edited by the editors at ScholarlyEditions™ and available exclusively from us. You now have a source you can cite with authority, confidence, and credibility. More information is available at http://www.ScholarlyEditions.com/.
Download or read book SELECTIVE DISSOLUTION OF URANIUM FROM FUEL FABRICATION SCRAP. written by and published by . This book was released on 1972 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 128 pages
Book Rating : 4.3/5 (91 download)
Download or read book Reprocessing of Irradiated Fission Reactor Fuel and Breeding Materials written by and published by . This book was released on 1958 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 726 pages
Book Rating : 4.3/5 (91 download)
Download or read book Reactor Fuel Processing written by and published by . This book was released on 1963 with total page 726 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : M. J. Whitman
Publisher :
ISBN 13 :
Total Pages : 204 pages
Book Rating : 4.3/5 (91 download)
Download or read book Report on Civilian Reactor Fuel Elements by the Civilian Reactor Fuel Element Review Group written by M. J. Whitman and published by . This book was released on 1959 with total page 204 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : W. W. Schulz
Publisher :
ISBN 13 :
Total Pages : 84 pages
Book Rating : 4.3/5 (91 download)
Download or read book Reprocessing of Low-enrichment Uranium-molybdenum Alloy Fuels written by W. W. Schulz and published by . This book was released on 1959 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 516 pages
Book Rating : 4.3/5 (91 download)
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1973 with total page 516 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : T. Kluth
Publisher :
ISBN 13 :
Total Pages : 5 pages
Book Rating : 4.:/5 (316 download)
Download or read book Recycling Of Uranium- And Plutonium-Contaminated Metals From Decommissioning Of The Hanau Fuel Fabrication Plant written by T. Kluth and published by . This book was released on 2003 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Decommissioning of a nuclear facility comprises not only actual dismantling but also, above all, management of the resulting residual materials and waste. Siemens Decommissioning Projects (DP) in Hanau has been involved in this task since 1995 when the decision was taken to decommission and dismantle the Hanau Fuel Fabrication Plant. Due to the decommissioning, large amounts of contaminated steel scrap have to be managed. The contamination of this metal scrap can be found almost exclusively in the form of surface contamination. Various decontamination technologies are involved, as there are blasting and wiping. Often these methods are not sufficient to meet the free release limits. In these cases, SIEMENS has decided to melt the scrap at Siempelkamp's melting plant. The plant is licensed according to the German Radiation Protection Ordinance Section 7 (issue of 20.07.2001). The furnace is a medium frequency induction type with a load capacity of 3.2 t and a throughput of 2 t/h for steel melting. For safety reasons, the furnace is widely operated by remote handling. A highly efficient filter system of cyclone, bag filter and HEPA-filter in two lines retains the dust and aerosol activity from the off-gas system. The slag is solidified at the surface of the melt and gripped before pouring the liquid iron into a chill. Since 1989, in total 15,000 t have been molten in the plant, 2,000 t of them having been contaminated steel scrap from the decommissioning of fuel fabrication plants. Decontamination factors could be achieved between 80 and 100 by the high affinity of the uranium to the slag former. The activity is transferred to the slag up to nearly 100 %. Samples taken from metal, slag and dust are analyzed by gamma measurements of the 186 keV line of U235 and the 1001 keV line of Pa234m for U238. All produced ingots showed a remaining activity less than 1 Bq/g and could be released for industrial reuse.
