000845583 001__ 845583
000845583 005__ 20240712084620.0
000845583 0247_ $$2doi$$a10.1016/j.jnucmat.2018.04.001
000845583 0247_ $$2ISSN$$a0022-3115
000845583 0247_ $$2ISSN$$a1873-4820
000845583 0247_ $$2WOS$$aWOS:000432845800012
000845583 037__ $$aFZJ-2018-02808
000845583 082__ $$a530
000845583 1001_ $$0P:(DE-HGF)0$$aMühr-Ebert, E. L.$$b0$$eCorresponding author
000845583 245__ $$aDissolution behavior of MgO based inert matrix fuel for the transmutation of minor actinides
000845583 260__ $$aAmsterdam [u.a.]$$bElsevier Science$$c2018
000845583 3367_ $$2DRIVER$$aarticle
000845583 3367_ $$2DataCite$$aOutput Types/Journal article
000845583 3367_ $$0PUB:(DE-HGF)16$$2PUB:(DE-HGF)$$aJournal Article$$bjournal$$mjournal$$s1525703108_17686
000845583 3367_ $$2BibTeX$$aARTICLE
000845583 3367_ $$2ORCID$$aJOURNAL_ARTICLE
000845583 3367_ $$00$$2EndNote$$aJournal Article
000845583 520__ $$aThis study explores the dissolution properties of magnesia-based inert matrix nuclear fuel (IMF) containing transuranium elements (TRU). Pure MgO pellets as well as MgO pellets containing CeO2, as surrogate for TRU oxides, and are considered as model systems for genuine magnesia based inert matrix fuel were fabricated. The aim of this study is to identify conditions at which the matrix material can be selectively dissolved during the head-end reprocessing step, allowing a separation of MgO from the actinides, whereas the actinides remain undissolved. The dissolution behavior was studied in macroscopic batch experiments as a function of nitric acid concentration, dissolution medium volume, temperature, stirring velocity, and pellet density (85, 90, 96, and 99%TD). To mimic pellets with various burn-ups the density of the here fabricated pellets was varied. MgO is soluble even under mild conditions (RT, 2.5 mol/L HNO3). The dissolution rates of MgO at different acid concentrations are rather similar, whereas the dissolution rate is strongly dependent on the temperature. Via a microscopic approach, a model was developed to describe the evolution of the pellet surface area during dissolution and determine a surface normalized dissolution rate. Moreover, dissolution rates of the inert matrix fuel containing CeO2 were determined as a function of the acid concentration and temperature. During the dissolution of MgO/CeO2 pellets the MgO dissolves completely, while CeO2 (>99%) remains undissolved. This study intends to provide a profound understanding of the chemical performance of magnesia based IMF containing fissile material. The feasibility of the dissolution of magnesia based IMF with nitric acid is discussed.
000845583 536__ $$0G:(DE-HGF)POF3-161$$a161 - Nuclear Waste Management (POF3-161)$$cPOF3-161$$fPOF III$$x0
000845583 536__ $$0G:(EU-Grant)295825$$aASGARD - Advanced fuelS for Generation IV reActors: Reprocessing and Dissolution (295825)$$c295825$$fFP7-Fission-2011$$x1
000845583 588__ $$aDataset connected to CrossRef
000845583 7001_ $$0P:(DE-Juel1)157852$$aLichte, E.$$b1
000845583 7001_ $$0P:(DE-Juel1)130329$$aBukaemskiy, A.$$b2$$ufzj
000845583 7001_ $$0P:(DE-Juel1)142526$$aFinkeldei, S.$$b3$$ufzj
000845583 7001_ $$0P:(DE-Juel1)130364$$aKlinkenberg, M.$$b4
000845583 7001_ $$0P:(DE-Juel1)144040$$aBrandt, F.$$b5
000845583 7001_ $$0P:(DE-Juel1)130324$$aBosbach, D.$$b6$$ufzj
000845583 7001_ $$0P:(DE-Juel1)130383$$aModolo, G.$$b7$$ufzj
000845583 773__ $$0PERI:(DE-600)2001279-2$$a10.1016/j.jnucmat.2018.04.001$$gVol. 505, p. 94 - 104$$p94 - 104$$tJournal of nuclear materials$$v505$$x0022-3115$$y2018
000845583 8564_ $$uhttps://juser.fz-juelich.de/record/845583/files/1-s2.0-S0022311517316148-main.pdf$$yRestricted
000845583 8564_ $$uhttps://juser.fz-juelich.de/record/845583/files/1-s2.0-S0022311517316148-main.gif?subformat=icon$$xicon$$yRestricted
000845583 8564_ $$uhttps://juser.fz-juelich.de/record/845583/files/1-s2.0-S0022311517316148-main.jpg?subformat=icon-1440$$xicon-1440$$yRestricted
000845583 8564_ $$uhttps://juser.fz-juelich.de/record/845583/files/1-s2.0-S0022311517316148-main.jpg?subformat=icon-180$$xicon-180$$yRestricted
000845583 8564_ $$uhttps://juser.fz-juelich.de/record/845583/files/1-s2.0-S0022311517316148-main.jpg?subformat=icon-640$$xicon-640$$yRestricted
000845583 8564_ $$uhttps://juser.fz-juelich.de/record/845583/files/1-s2.0-S0022311517316148-main.pdf?subformat=pdfa$$xpdfa$$yRestricted
000845583 909CO $$ooai:juser.fz-juelich.de:845583$$pec_fundedresources$$pVDB$$popenaire
000845583 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)130329$$aForschungszentrum Jülich$$b2$$kFZJ
000845583 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)142526$$aForschungszentrum Jülich$$b3$$kFZJ
000845583 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)130364$$aForschungszentrum Jülich$$b4$$kFZJ
000845583 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)144040$$aForschungszentrum Jülich$$b5$$kFZJ
000845583 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)130324$$aForschungszentrum Jülich$$b6$$kFZJ
000845583 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)130383$$aForschungszentrum Jülich$$b7$$kFZJ
000845583 9131_ $$0G:(DE-HGF)POF3-161$$1G:(DE-HGF)POF3-160$$2G:(DE-HGF)POF3-100$$3G:(DE-HGF)POF3$$4G:(DE-HGF)POF$$aDE-HGF$$bEnergie$$lNukleare Entsorgung und Sicherheit sowie Strahlenforschung$$vNuclear Waste Management$$x0
000845583 9141_ $$y2018
000845583 915__ $$0StatID:(DE-HGF)0420$$2StatID$$aNationallizenz
000845583 915__ $$0StatID:(DE-HGF)0100$$2StatID$$aJCR$$bJ NUCL MATER : 2015
000845583 915__ $$0StatID:(DE-HGF)0200$$2StatID$$aDBCoverage$$bSCOPUS
000845583 915__ $$0StatID:(DE-HGF)0600$$2StatID$$aDBCoverage$$bEbsco Academic Search
000845583 915__ $$0StatID:(DE-HGF)0030$$2StatID$$aPeer Review$$bASC
000845583 915__ $$0StatID:(DE-HGF)0199$$2StatID$$aDBCoverage$$bThomson Reuters Master Journal List
000845583 915__ $$0StatID:(DE-HGF)0110$$2StatID$$aWoS$$bScience Citation Index
000845583 915__ $$0StatID:(DE-HGF)0150$$2StatID$$aDBCoverage$$bWeb of Science Core Collection
000845583 915__ $$0StatID:(DE-HGF)0111$$2StatID$$aWoS$$bScience Citation Index Expanded
000845583 915__ $$0StatID:(DE-HGF)1150$$2StatID$$aDBCoverage$$bCurrent Contents - Physical, Chemical and Earth Sciences
000845583 915__ $$0StatID:(DE-HGF)1160$$2StatID$$aDBCoverage$$bCurrent Contents - Engineering, Computing and Technology
000845583 915__ $$0StatID:(DE-HGF)9900$$2StatID$$aIF < 5
000845583 920__ $$lyes
000845583 9201_ $$0I:(DE-Juel1)IEK-6-20101013$$kIEK-6$$lNukleare Entsorgung und Reaktorsicherheit$$x0
000845583 980__ $$ajournal
000845583 980__ $$aVDB
000845583 980__ $$aI:(DE-Juel1)IEK-6-20101013
000845583 980__ $$aUNRESTRICTED
000845583 981__ $$aI:(DE-Juel1)IFN-2-20101013