Hauptseite > Publikationsdatenbank > An Overview of Solvent Extraction Processes Developed in Europe for Advanced Nuclear Fuel Recycling, Part 1 — Heterogeneous Recycling > print

001     878110
005     20240708133812.0
024 7 _ |a 10.1080/01496395.2020.1795680
|2 doi
024 7 _ |a 0037-2366
|2 ISSN
024 7 _ |a 0037-2404
|2 ISSN
024 7 _ |a 0149-6395
|2 ISSN
024 7 _ |a 1520-5754
|2 ISSN
024 7 _ |a 2332-3957
|2 ISSN
024 7 _ |a 2128/27928
|2 Handle
024 7 _ |a WOS:000553287800001
|2 WOS
037 _ _ |a FZJ-2020-02637
041 _ _ |a English
082 _ _ |a 540
100 1 _ |a Geist, Andreas
|0 0000-0003-1436-8247
|b 0
|e Corresponding author
245 _ _ |a An Overview of Solvent Extraction Processes Developed in Europe for Advanced Nuclear Fuel Recycling, Part 1 — Heterogeneous Recycling
260 _ _ |a London
|c 2021
|b Informa plc
336 7 _ |a article
|2 DRIVER
336 7 _ |a Output Types/Journal article
|2 DataCite
336 7 _ |a Journal Article
|b journal
|m journal
|0 PUB:(DE-HGF)16
|s 1646221933_5185
|2 PUB:(DE-HGF)
336 7 _ |a ARTICLE
|2 BibTeX
336 7 _ |a JOURNAL_ARTICLE
|2 ORCID
336 7 _ |a Journal Article
|0 0
|2 EndNote
520 _ _ |a The hydrometallurgical separation concepts for the heterogeneous recycling of irradiatednuclear fuel developed within European collaborative projects are presented and discussed. Most ofthese concepts were developed within European collaborative projects and involve solvent extractionprocesses separating trivalent minor actinides (with a focus on americium) from the raffinate solutionfrom processes such as PUREX (Plutonium Uranium Reduction Extraction) or an evolution ofPUREX. Depending on the process chemistry applied, process schemes each consisting of one, twoor three solvent extraction cycles are required to obtain a pure americium product. The various solventextraction processes are briefly introduced. The most suitable choices are selected and the processschemes are compared to one another.
536 _ _ |a 1411 - Nuclear Waste Disposal (POF4-141)
|0 G:(DE-HGF)POF4-1411
|c POF4-141
|f POF IV
|x 0
536 _ _ |a GENIORS - GEN IV Integrated Oxide fuels recycling strategies (755171)
|0 G:(EU-Grant)755171
|c 755171
|f NFRP-2016-2017-1
|x 1
588 _ _ |a Dataset connected to CrossRef
700 1 _ |a Adnet, Jean-Marc
|0 P:(DE-HGF)0
|b 1
700 1 _ |a Bourg, Stéphane
|0 P:(DE-HGF)0
|b 2
700 1 _ |a Ekberg, Christian
|0 0000-0002-0065-7673
|b 3
700 1 _ |a Galán, Hitos
|0 P:(DE-HGF)0
|b 4
700 1 _ |a Guilbaud, Philippe
|0 0000-0001-9777-8326
|b 5
700 1 _ |a Miguirditchian, Manuel
|0 0000-0002-7676-757X
|b 6
700 1 _ |a Modolo, Giuseppe
|0 P:(DE-Juel1)130383
|b 7
700 1 _ |a Rhodes, Chris
|0 P:(DE-HGF)0
|b 8
700 1 _ |a Taylor, Robin
|0 P:(DE-HGF)0
|b 9
773 _ _ |a 10.1080/01496395.2020.1795680
|g p. 1 - 16
|0 PERI:(DE-600)2015452-5
|n 11
|p 1866-1881
|t Separation science and technology
|v 56
|y 2021
|x 1520-5754
856 4 _ |u https://juser.fz-juelich.de/record/878110/files/Accepted%20Manuscript.pdf
|y Published on 2020-07-27. Available in OpenAccess from 2021-07-27.
|z StatID:(DE-HGF)0510
909 C O |o oai:juser.fz-juelich.de:878110
|p openaire
|p open_access
|p driver
|p VDB
|p ec_fundedresources
|p dnbdelivery
910 1 _ |a Forschungszentrum Jülich
|0 I:(DE-588b)5008462-8
|k FZJ
|b 7
|6 P:(DE-Juel1)130383
913 1 _ |a DE-HGF
|b Forschungsbereich Energie
|l Nukleare Entsorgung, Sicherheit und Strahlenforschung (NUSAFE II)
|1 G:(DE-HGF)POF4-140
|0 G:(DE-HGF)POF4-141
|3 G:(DE-HGF)POF4
|2 G:(DE-HGF)POF4-100
|4 G:(DE-HGF)POF
|v Nukleare Entsorgung
|9 G:(DE-HGF)POF4-1411
|x 0
913 0 _ |a DE-HGF
|b Energie
|l Nukleare Entsorgung und Sicherheit sowie Strahlenforschung
|1 G:(DE-HGF)POF3-160
|0 G:(DE-HGF)POF3-161
|3 G:(DE-HGF)POF3
|2 G:(DE-HGF)POF3-100
|4 G:(DE-HGF)POF
|v Nuclear Waste Management
|x 0
914 1 _ |y 2021
915 _ _ |a DBCoverage
|0 StatID:(DE-HGF)0200
|2 StatID
|b SCOPUS
|d 2020-01-17
915 _ _ |a DBCoverage
|0 StatID:(DE-HGF)0160
|2 StatID
|b Essential Science Indicators
|d 2020-01-17
915 _ _ |a DBCoverage
|0 StatID:(DE-HGF)0600
|2 StatID
|b Ebsco Academic Search
|d 2020-01-17
915 _ _ |a Embargoed OpenAccess
|0 StatID:(DE-HGF)0530
|2 StatID
915 _ _ |a JCR
|0 StatID:(DE-HGF)0100
|2 StatID
|b SEP SCI TECHNOL : 2018
|d 2020-01-17
915 _ _ |a Creative Commons Attribution-NonCommercial CC BY-NC 4.0
|0 LIC:(DE-HGF)CCBYNC4
|2 HGFVOC
915 _ _ |a DBCoverage
|0 StatID:(DE-HGF)0150
|2 StatID
|b Web of Science Core Collection
|d 2020-01-17
915 _ _ |a WoS
|0 StatID:(DE-HGF)0110
|2 StatID
|b Science Citation Index
|d 2020-01-17
915 _ _ |a WoS
|0 StatID:(DE-HGF)0111
|2 StatID
|b Science Citation Index Expanded
|d 2020-01-17
915 _ _ |a IF < 5
|0 StatID:(DE-HGF)9900
|2 StatID
|d 2020-01-17
915 _ _ |a Peer Review
|0 StatID:(DE-HGF)0030
|2 StatID
|b ASC
|d 2020-01-17
915 _ _ |a DBCoverage
|0 StatID:(DE-HGF)1150
|2 StatID
|b Current Contents - Physical, Chemical and Earth Sciences
|d 2020-01-17
915 _ _ |a DBCoverage
|0 StatID:(DE-HGF)0300
|2 StatID
|b Medline
|d 2020-01-17
915 _ _ |a Nationallizenz
|0 StatID:(DE-HGF)0420
|2 StatID
|d 2020-01-17
|w ger
915 _ _ |a DBCoverage
|0 StatID:(DE-HGF)0199
|2 StatID
|b Clarivate Analytics Master Journal List
|d 2020-01-17
920 _ _ |l yes
920 1 _ |0 I:(DE-Juel1)IEK-6-20101013
|k IEK-6
|l Nukleare Entsorgung und Reaktorsicherheit
|x 0
980 1 _ |a FullTexts
980 _ _ |a journal
980 _ _ |a VDB
980 _ _ |a I:(DE-Juel1)IEK-6-20101013
980 _ _ |a UNRESTRICTED
981 _ _ |a I:(DE-Juel1)IFN-2-20101013

LibraryCollectionCLSMajorCLSMinorLanguageAuthor
Marc 21