| 001 | 864726 | ||
| 005 | 20240708133903.0 | ||
| 037 | _ | _ | |a FZJ-2019-04397 |
| 100 | 1 | _ | |a Altmaier, Marcus |0 P:(DE-HGF)0 |b 0 |e Corresponding author |
| 111 | 2 | _ | |a Goldschmidt 2019 |c Barcelona |d 2019-08-18 - 2019-08-23 |w Spain |
| 245 | _ | _ | |a VESPA 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 |
| 260 | _ | _ | |c 2019 |
| 336 | 7 | _ | |a Conference Paper |0 33 |2 EndNote |
| 336 | 7 | _ | |a INPROCEEDINGS |2 BibTeX |
| 336 | 7 | _ | |a conferenceObject |2 DRIVER |
| 336 | 7 | _ | |a CONFERENCE_POSTER |2 ORCID |
| 336 | 7 | _ | |a Output Types/Conference Poster |2 DataCite |
| 336 | 7 | _ | |a Poster |b poster |m poster |0 PUB:(DE-HGF)24 |s 1567690420_30741 |2 PUB:(DE-HGF) |x Other |
| 520 | _ | _ | |a The 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. |
| 536 | _ | _ | |a 161 - Nuclear Waste Management (POF3-161) |0 G:(DE-HGF)POF3-161 |c POF3-161 |f POF III |x 0 |
| 700 | 1 | _ | |a Bischofer, Barbara |0 P:(DE-HGF)0 |b 1 |
| 700 | 1 | _ | |a Bosbach, Dirk |0 P:(DE-Juel1)130324 |b 2 |u fzj |
| 700 | 1 | _ | |a Brendler, Vinzenz |0 P:(DE-HGF)0 |b 3 |
| 700 | 1 | _ | |a Daniels, Natalia |0 P:(DE-Juel1)166149 |b 4 |u fzj |
| 700 | 1 | _ | |a Geckeis, Horst |0 P:(DE-HGF)0 |b 5 |
| 700 | 1 | _ | |a Hagemann, Sven |0 P:(DE-HGF)0 |b 6 |
| 700 | 1 | _ | |a Müller, Katharina |0 P:(DE-HGF)0 |b 7 |
| 909 | C | O | |o oai:juser.fz-juelich.de:864726 |p VDB |
| 910 | 1 | _ | |a Forschungszentrum Jülich |0 I:(DE-588b)5008462-8 |k FZJ |b 2 |6 P:(DE-Juel1)130324 |
| 910 | 1 | _ | |a Forschungszentrum Jülich |0 I:(DE-588b)5008462-8 |k FZJ |b 4 |6 P:(DE-Juel1)166149 |
| 913 | 1 | _ | |a DE-HGF |l Nukleare Entsorgung und Sicherheit sowie Strahlenforschung |1 G:(DE-HGF)POF3-160 |0 G:(DE-HGF)POF3-161 |2 G:(DE-HGF)POF3-100 |v Nuclear Waste Management |x 0 |4 G:(DE-HGF)POF |3 G:(DE-HGF)POF3 |b Energie |
| 914 | 1 | _ | |y 2019 |
| 920 | 1 | _ | |0 I:(DE-Juel1)IEK-6-20101013 |k IEK-6 |l Nukleare Entsorgung und Reaktorsicherheit |x 0 |
| 980 | _ | _ | |a poster |
| 980 | _ | _ | |a VDB |
| 980 | _ | _ | |a I:(DE-Juel1)IEK-6-20101013 |
| 980 | _ | _ | |a UNRESTRICTED |
| 981 | _ | _ | |a I:(DE-Juel1)IFN-2-20101013 |
| Library | Collection | CLSMajor | CLSMinor | Language | Author |
|---|
Gast ::