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The INE-Beamline for actinide science at ANKA

Review of scientific instruments, 2012-04, Vol.83 (4), p.043105-043105-13

2012

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Instant release of fission products in leaching experiments with high burn-up nuclear fuels in the framework of the Euratom project FIRST- Nuclides

Journal of nuclear materials, 2017-02, Vol.484, p.307-323

2017

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

Journal of nuclear materials, 2016-10, Vol.479, p.67-75

2016

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

Journal of nuclear materials, 2015-05, Vol.460, p.209-215

2015

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Corrosion behavior of spent nuclear fuel in high pH solutions – Effect of hydrogen

MRS proceedings, 2012, Vol.1475 (1), p.119-124, Article imrc11-1475-nw35-o27

2012

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Effects of humic substances on the [formula omitted] migration in a sandy aquifer: column experiments with Gorleben groundwater/sediment systems

Journal of contaminant hydrology, 1998-12, Vol.35 (1), p.261-275

1998

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

Journal of physics. Conference series, 2013-01, Vol.430 (1), p.12114-5

2013

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Galvanic Corrosion between the Nuclear Waste Disposal Container Material Pairs of Copper-Nickel Alloys and Carbon Steel in Salt Brines

Corrosion (Houston, Tex.), 2005-03, Vol.61 (3), p.230-236

2005

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Determination of sorption isotherms for Eu, Th, U and Am on the gel layer of corroded HLW glass

Journal of nuclear materials, 2001-09, Vol.298 (1), p.155-162

2001

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Corrosion Behavior of High Burnup Spent Fuel in Highly Alkaline Solutions

MRS proceedings, 2009, Vol.1193 (1), Article 597

2009

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

Journal of contaminant hydrology, 2003-03, Vol.61 (1), p.265-279

2003

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

Radiochimica acta, 2012-01, Vol.100 (8-9), p.699-713

2012

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

Physics and chemistry of the earth. Parts A/B/C, 2013, Vol.64, p.87-94

2013

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Fast/Instant Radionuclide Release: Effects inherent to the experiment

MRS proceedings, 2014, Vol.1665 (1), p.233-243

2014

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Redox processes in the safety case of deep geological repositories of radioactive wastes. Contribution of the European RECOSY Collaborative Project

Applied geochemistry, 2014-10, Vol.49, p.206-217

2014

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Redox processes in the safety case of deep geological repositories of radioactive wastes. Contribution of the European RECOSY Collaborative Project: Geochemistry for Risk Assessment: Hazardous waste in the Geosphere

Applied geochemistry, 2014, Vol.49, p.206-217

2014

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Swedish-German actinide migration experiment at ÄSPÖ hard rock laboratory

Journal of contaminant hydrology, 2003-03, Vol.61 (1), p.219-233

2003

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

Nuclear technology, 2017-06, Vol.198 (3), p.260-276

2017

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

Physics and chemistry of the earth. Parts A/B/C, 2014, Vol.70-71, p.53-59

2014

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

Journal of nuclear materials, 2005-11, Vol.346 (1), p.24-31

2005

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Characterization and radionuclide retention properties of heat-treated concrete

Physics and chemistry of the earth. Parts A/B/C, 2014, Vol.70-71, p.45-52

2014

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Long-Term Leaching Experiments of Full-Scale Cemented Waste Forms: Experiments and Modeling

Nuclear technology, 2000-01, Vol.129 (1), p.101-118

2000

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Dissolution of spent nuclear fuel fragments at high alkaline conditions under H2 overpressure

MRS advances, 2016, Vol.1 (62), p.4163-4168

2016

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

Radiochimica acta, 2010-01, Vol.98 (9-11), p.674-683

2010

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Modeling of Near Field Actinide Concentrations in Radioactive Waste Repositories in Salt Formations: Effect of Buffer Materials

MRS proceedings, 2000, Vol.663, Article 791

2000

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The INE-Beamline for actinide science at ANKA

Instant release of fission products in leaching experiments with high burn-up nuclear fuels in the framework of the Euratom project FIRST- Nuclides

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

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

Corrosion behavior of spent nuclear fuel in high pH solutions – Effect of hydrogen

Effects of humic substances on the [formula omitted] migration in a sandy aquifer: column experiments with Gorleben groundwater/sediment systems

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

Galvanic Corrosion between the Nuclear Waste Disposal Container Material Pairs of Copper-Nickel Alloys and Carbon Steel in Salt Brines

Determination of sorption isotherms for Eu, Th, U and Am on the gel layer of corroded HLW glass

Corrosion Behavior of High Burnup Spent Fuel in Highly Alkaline Solutions

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

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

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

Fast/Instant Radionuclide Release: Effects inherent to the experiment

Redox processes in the safety case of deep geological repositories of radioactive wastes. Contribution of the European RECOSY Collaborative Project

Redox processes in the safety case of deep geological repositories of radioactive wastes. Contribution of the European RECOSY Collaborative Project: Geochemistry for Risk Assessment: Hazardous waste in the Geosphere

Swedish-German actinide migration experiment at ÄSPÖ hard rock laboratory

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

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

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

Characterization and radionuclide retention properties of heat-treated concrete

Long-Term Leaching Experiments of Full-Scale Cemented Waste Forms: Experiments and Modeling

Dissolution of spent nuclear fuel fragments at high alkaline conditions under H2 overpressure

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

Modeling of Near Field Actinide Concentrations in Radioactive Waste Repositories in Salt Formations: Effect of Buffer Materials

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