000864726 001__ 864726
000864726 005__ 20240708133903.0
000864726 037__ $$aFZJ-2019-04397
000864726 1001_ $$0P:(DE-HGF)0$$aAltmaier, Marcus$$b0$$eCorresponding author
000864726 1112_ $$aGoldschmidt 2019$$cBarcelona$$d2019-08-18 - 2019-08-23$$wSpain
000864726 245__ $$aVESPA II Project: Behavior of Long-Lived Fission and Activation Products in the Near-Field of a Repository for Nuclear Waste and Possibilities of their Retention
000864726 260__ $$c2019
000864726 3367_ $$033$$2EndNote$$aConference Paper
000864726 3367_ $$2BibTeX$$aINPROCEEDINGS
000864726 3367_ $$2DRIVER$$aconferenceObject
000864726 3367_ $$2ORCID$$aCONFERENCE_POSTER
000864726 3367_ $$2DataCite$$aOutput Types/Conference Poster
000864726 3367_ $$0PUB:(DE-HGF)24$$2PUB:(DE-HGF)$$aPoster$$bposter$$mposter$$s1567690420_30741$$xOther
000864726 520__ $$aThe German project VESPA II (www.vespa2.grs.de) aims at studying  the chemical  properties of  fission(FPs) and activation products (APs), 137Cs, 129I, 99Tc, and 79Se, as well as their transport behavior under conditions of near-field of a nuclear waste repository. This knowledge is mandatory for a safe and  reliable long-term  assessment  of  high-level radioactive   waste disposal avoiding conservative assumptions. The  work  performed  within VESPA II provides for the necessary links between important aspects of the management of FPs and APs in deep geological repositories. In particular, we  investigate: (1) the  source  term, evaluating e.g. 129I inventory  together  with  the  instant  release  fraction  and  its speciation; (2) the effect  of geochemical  conditions in the near-field, i.e. T, p, Eh and pH, on  the processes of surface redox-mediation and secondary mineral phases formation; (3) the solution chemistry, determining stable solubility products, complex  formation  and  activity  coefficients  of  Tc(IV)  in presence  of  anions,  Tc(VII)  in  presence  of  cations,  Se(-II) under  acidic  conditions  and  Se(IV),  Se(0),  Cs(I),  I(-I)  at elevated temperature; and (4) the retention behavior of I, Se and  Tc  on  layered  double  hydroxides  (LDH),  Fe-corrosion phases  and  on  calcite.  Finally, safety  analysis calculations will link obtained results and  provide for  an improved confidence in the risk assessment predictions.
000864726 536__ $$0G:(DE-HGF)POF3-161$$a161 - Nuclear Waste Management (POF3-161)$$cPOF3-161$$fPOF III$$x0
000864726 7001_ $$0P:(DE-HGF)0$$aBischofer, Barbara$$b1
000864726 7001_ $$0P:(DE-Juel1)130324$$aBosbach, Dirk$$b2$$ufzj
000864726 7001_ $$0P:(DE-HGF)0$$aBrendler, Vinzenz$$b3
000864726 7001_ $$0P:(DE-Juel1)166149$$aDaniels, Natalia$$b4$$ufzj
000864726 7001_ $$0P:(DE-HGF)0$$aGeckeis, Horst$$b5
000864726 7001_ $$0P:(DE-HGF)0$$aHagemann, Sven$$b6
000864726 7001_ $$0P:(DE-HGF)0$$aMüller, Katharina$$b7
000864726 909CO $$ooai:juser.fz-juelich.de:864726$$pVDB
000864726 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)130324$$aForschungszentrum Jülich$$b2$$kFZJ
000864726 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)166149$$aForschungszentrum Jülich$$b4$$kFZJ
000864726 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
000864726 9141_ $$y2019
000864726 9201_ $$0I:(DE-Juel1)IEK-6-20101013$$kIEK-6$$lNukleare Entsorgung und Reaktorsicherheit$$x0
000864726 980__ $$aposter
000864726 980__ $$aVDB
000864726 980__ $$aI:(DE-Juel1)IEK-6-20101013
000864726 980__ $$aUNRESTRICTED
000864726 981__ $$aI:(DE-Juel1)IFN-2-20101013