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BROCTIO - Bentonite powder water content
control by water vapour equilibrium
technique for mechanical tests. |
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BROCTIO - Thermal evolution and thermally induced stress simulation of SNF repository |
|
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DEMONI - Research notes 2020 C14_steel dissolution |
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KARAHDE - Effect of burnable absorber rods and U-235 enrichment on EPR UO2 fuel assembly source term with Serpent 2 |
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KARAHDE - Evaluating the Effect of Decay and Fission Yield Data Uncertainty on BWR Spent Nuclear Fuel Source |
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KARAHDE - Impact of approximation in operating history data on spent fuel properties with Serpent 2 |
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KARAHDE - Impurity-generated impact on the characteristics of spent nuclear fuel |
|
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KARAHDE - Separate effect of decay and fission yield data uncertainty on spent nuclear fuel source term |
|
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KARAHDE - The Effect of Calculation Parameters on Spent Nuclear Fuel Source Term |
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KUKO - Vuosiraportti 2019 |
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MiBe - Mikrobien vaikutukset bentoniitissa 2020 |
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PORA - BISON mesh generation script for analysis of cracked fuel pellets |
|
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RASK - Comparison of autoradioraphies for the porosity of altered rocks |
|
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SOLID - Role of the host communities in
final disposal of spent nuclear fuel in
Finland and Sweden |
|
|
SUCCESS - Re-passivation rate of Cu-OFP |
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SURFACE - Performance of a Landfill-Type Near Surface Repository VTT-R-00016-21 |
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SURFACE - Near Surface Repositories in Finland 2019 vuosiraportti |
|
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SYSMET - Nuclear Waste repository as a
scenario problem - Developing epistemic
understanding |
|
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TERKOR - Vuosiraportti 2019 |
|
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DEMONI - Review: Radionuclide leaching in
concrete containment barriers |
|
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DEMONI - Review: Influence of radiation on
concrete mechanical properties |
|
|
KÄRÄHDE - Impact of Fuel Type and Discharge
Burnup on Spent Fuel Properties - SYP2019 |
|
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KÄRÄHDE - Impact of Fuel Type and Discharge
Burnup on Source Term - NENE2019 |
|
|
KÄRÄHDE - Evaluating the Effect of Decay and
Fission Yield Data Uncertainty on Spent
Nuclear Fuel Source Term Using Serpent 2 -
NENE2019 |
|
|
KÄRÄHDE - Evaluating the effect of decay and fission yield data uncertainty on spent nuclear fuel source term using Serpent 2 – continued study |
|
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KÄRÄHDE - Impurities in LWR fuel and structural materials |
|
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MiBe tutkimusraportti 2019 - Mikrobien vaikutukset bentoniitissa |
|
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OMT – Overall Safety of Nuclear Waste Disposal |
|
|
RASK - Mineralogical and microstructural
evolution of Portland cement paste/argillite
interfaces at 70 °C – Considerations for
diffusion and porosity properties |
|
|
RASK - Electronic autoradiography of 133Ba
particle emissions; diffusion profiles in
granitic rocks |
|
|
RASK - Sorption of selenium species onto
phlogopite and calcite surfaces: DFT studies |
|
|
SURFACE - Near Surface Repositories in Finland |
