V. Metz

发表

Stirring effect on kaolinite dissolution rate

J. Ganor, V. Metz, 2001 .

Effects of hydrogen and bromide on the corrosion of spent nuclear fuel and γ-irradiated UO2(s) in NaCl brine

Volker Metz, Dieter Schild, E. Bohnert, 2008 .

Model uncertainty for the mechanism of dissolution of spent fuel in nuclear waste repository.

E. Iglesias, Christelle Martin, M. Jonsson, 2010 .

1st Annual Workshop Proceedings of the Collaborative Project "Fast / Instant Release of Safety Relevant Radionuclides from Spent Nuclear Fuel" (7th EC FP CP FIRST-Nuclides), Budapest 09 - 11 October 2012 (KIT Scientific Reports ; 7639)

V. Metz, L. Duro, B. Kienzler, 2013 .

Co-precipitation of radium in high ionic strength systems: 1. Thermodynamic properties of the Na–Ra–Cl–SO4–H2O system – Estimating Pitzer parameters for RaCl2

J. Ganor, V. Metz, Y. Rosenberg, 2011 .

Co-precipitation of radium in high ionic strength systems: 2. Kinetic and ionic strength effects

J. Ganor, Y. Volkman, V. Metz, 2011 .

Determination of fission gas release of spent nuclear fuel in puncturing test and in leaching experiments under anoxic conditions

V. Metz, W. D. Weerd, D. Papaioannou, 2016 .

The effect of pH and temperature on kaolinite dissolution rate under acidic conditions

J. Ganor, J. Cama, V. Metz, 2002 .

CEBAMA ( Contract Number : 662147 ) Deliverable D 3 . 02 Review and definition of modelling approaches : scale of analysis , physico-chemical processes , software , HPC resources

J. Samper, L. Montenegro, J. Shao, 2016 .

Stoichiometry of smectite dissolution reaction

J. Ganor, V. Metz, K. Amram, 2005 .

Summary of the Euratom Collaborative Project FIRST-Nuclides and Conclusions for the Safety Case

J. de Pablo, L. Johnson, K. Spahiu, 2017 .

Fast / Instant Release of Safety Relevant Radionuclides from Spent Nuclear Fuel FIRST-Nuclides

V. Metz, D. Papaioannou, V. Rondinella, 2012 .

Combining thermodynamic simulations, element and surface analytics to study U(VI) retention in corroded cement monoliths upon >20 years of leaching

D. Schild, V. Metz, K. Dardenne, 2014 .

Monte-Carlo based investigation of individual dosimetry in deep geological repository for high-level nuclear waste with consideration of realistic body postures

V. Metz, F. Becker, B. Pang, 2021 .

Comparison of calculated and measured radionuclide inventory of a Zircaloy-4 cladding tube plenum section

V. Metz, R. Dagan, E. González-Robles, 2018 .

Interaction of hydrogen with radiolysis products in NaCl solution — comparing pulse radiolysis experiments with simulations

E. Janata, M. Kelm, V. Metz, 2011 .

Characterization and radionuclide retention properties of heat-treated concrete

A. Miassoedov, V. Metz, B. Kienzler, 2014 .

Radionuclide behaviour in the near-field of a geological repository for spent nuclear fuel

V. Metz, A. Loida, B. Kienzler, 2012 .

Solid-liquid equilibria of Mg(OH)2(cr) and Mg2(OH)3Cl·4H2O(cr) in the system Mg-Na-H-OH-Cl-H2O at 25°C

V. Metz, T. Fanghänel, M. Altmaier, 2003 .

Adsorption of dissolved aluminum on sapphire-c and kaolinite: implications for points of zero charge of clay minerals

V. Metz, R. Weerasooriya, J. Lützenkirchen, 2014, Geochemical Transactions.

Barite recrystallization in the presence of 226Ra and 133Ba

E. Curti, V. Metz, H. Geckeis, 2018, Geochimica et Cosmochimica Acta.

Fifteen Years of Radionuclide Research at the KIT Synchrotron Source in the Context of the Nuclear Waste Disposal Safety Case

D. Schild, E. Corrales, V. Metz, 2019, Geosciences.

FLUKA study of the actinides induced irradiation damage in Zircaloy-4 cladding during interim dry storage

V. Metz, S. Manenti, M. Herm, 2022, Journal of Nuclear Materials.

Reactive Transport Modelling of the Long-Term Interaction between Carbon Steel and MX-80 Bentonite at 25 °C

M. Chaparro, V. Metz, H. Geckeis, 2021, Minerals.

Surface protonation data of kaolinite-reevaluation based on dissolution experiments.

J. Ganor, J. Cama, V. Metz, 2003, Journal of colloid and interface science.

Mineralogical characterization of scalings formed in geothermal sites in the Upper Rhine Graben before and after the application of sulfate inhibitors

Sabine Jähnichen, D. Schild, T. Schäfer, 2018 .

XAS and XRF investigation of an actual HAWC glass fragment obtained from the Karlsruhe vitrification plant (VEK)

V. Metz, K. Dardenne, B. Kienzler, 2015 .

Chemical status of U(VI) in cemented waste forms under saline conditions

D. Schild, V. Metz, B. Kienzler, 2010 .

Schlieker Long-Term Interactions of Full-Scale Cemented Waste Simulates with Salt

V. Metz, B. Kienzler, C. Borkel, 2016 .

Characterization of U(VI)-phases in corroded cement products by micro(μ)-spectroscopic methods

T. Prüssmann, D. Schild, V. Metz, 2013 .

Radionuclide Source Term for HLW Glass, Spent Nuclear Fuel, and Compacted Hulls and End Pieces (CSD-C Waste) (KIT Scientific Reports ; 7624)

Marcus Altmaier, Volker Metz, Bernhard Kienzler, 2012 .

Radionuclide release from high burnup spent fuel during corrosion in salt brine in the presence of hydrogen overpressure

Volker Metz, Horst Geckeis, Bernhard Kienzler, 2005 .

Impact of Hydrogen Overpressure on Spent Fuel Alteration Behavior in Salt Brine During a Three-Year Long Corrosion Test

V. Metz, A. Loida, B. Kienzler, 2004 .

Nucleation and growth kinetics of RaxBa1−xSO4 solid solution in NaCl aqueous solutions

J. Ganor, V. Metz, C. Pina, 2014 .

Net surface proton excess of smectites obtained from a combination of potentiometric acid-base, mass and electrolyte titrations

A. Bauer, S. Sjöberg, V. Metz, 2012 .

Towards the establishment of a reliable proxy for the reactive surface area of smectite

J. Ganor, D. Bosbach, V. Metz, 2005 .

Stoichiometry of smectite dissolution reaction-108 / 10 / 04 Stoichiometry of smectite dissolution reaction

J. Ganor, V. Metz, K. Amram, 2004 .

The INE-Beamline for actinide science at ANKA.

C. Walther, V. Metz, M. Denecke, 2012, The Review of scientific instruments.

Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo

M. Verwerft, I. Farnan, D. Bosbach, 2023, EPJ Nuclear Sciences & Technologies.

Radium removal in a large scale evaporitic system

J. Ganor, V. Metz, Y. Rosenberg, 2013 .

Geochemically derived non-gaseous radionuclide source term for the Asse salt mine – assessment for the use of a Mg(OH)2-based backfill material

Volker Metz, Thomas Fanghänel, B. Kienzler, 2004 .

Long-term cement corrosion in chloride-rich solutions relevant to radioactive waste disposal in rock salt – Leaching experiments and thermodynamic simulations

Volker Metz, Bernhard Kienzler, Dieter Schild, 2013 .

TRePro 2002 - modelling of coupled transport reaction processes. Workshop of the Forschungszentrum Karlsruhe held at 20th and 21st of March 2002

V. Metz, J. Lützenkirchen, W. Pfingsten, 2002 .

Geochemical evaluation of different groundwater-host rock systems for radioactive waste disposal.

V. Metz, B. Kienzler, W. Schüssler, 2003, Journal of Contaminant Hydrology.

Geochemically Based Safety Assessment

E. Korthaus, V. Metz, T. Fanghänel, 2007 .

Alteration Behavior of High Burnup Spent Fuel in Salt Brine Under Hydrogen Overpressure and in Presence of Bromide

Volker Metz, Bernhard Kienzler, V. Metz, 2006 .

Radionuclide Source Term for Irradiated Fuel from Prototype, Research and Education Reactors, for Waste Forms with Negligible Heat Generation and for Uranium Tails (KIT Scientific Reports ; 7635)

Marcus Altmaier, Volker Metz, Bernhard Kienzler, 2013 .

Anaerobic corrosion of carbon steel in compacted bentonite exposed to natural Opalinus clay porewater: Bentonite alteration study.

N. Diomidis, D. Schild, V. Metz, 2021, Goldschmidt2021 abstracts.

Study of the release of the fission gases (Xe and Kr) and the fision products (Cs and I) under anoxic conditions in bicarbonate water

V. Montoya, V. Metz, E. Bohnert, 2015 .

Fast/Instant Radionuclide Release: Effects inherent to the experiment

V. Metz, A. Loida, B. Kienzler, 2014 .

Physico-chemical characterization of a spent UO2 fuel with respect to its stability under final disposal conditions

V. Metz, D. Papaioannou, E. Bohnert, 2014 .

Solid-liquid equilibria of Sorel phases and Mg (OH)2 in the system Na-Mg-Cl-OH-H2O. Part I: experimental determination of OH− and H+ equilibrium concentrations and solubility constants at 25°C, 40°C, and 60°C

W. Voigt, V. Metz, M. Pannach, 2023, Frontiers in Nuclear Engineering.

Formation of (Ba,Ra)SO4 Solid Solutions – Results from Barite (Re)Precipitation and Coprecipitation Experiments

J. Ganor, D. Bosbach, V. Metz, 2011 .

Previous investigations on the instant release fraction and general description of the project

Volker Metz, A. Valls, Olga Riba, 2013 .