Finnish spent nuclear fuel is planned to be disposed of deep in the crystalline bedrock of the Olkiluoto island. In such a repository, the role of the bentonite buffer is considered to be central. The initially unsaturated bentonite emplaced around a spent-fuel canister will become fully saturated by the groundwater from the host rock. In order to assess the long-term safety of a deep repository, it is essential to determine how temperature influences the chemical stability of bentonite. The aim of this study was to achieve an improved understanding of the factors governing the thermo-hydro-chemical evolution of the bentonite buffer subject to heat generation from the disposed fuel and in contact with a highly permeable rock fracture inters...
Compacted bentonite is commonly considered for use as backfill material in emplacement tunnels of nu...
The Long-Term Test of Buffer Material (LOT) is underway in the Äspö Hard Rock Laboratory in Sweden. ...
Subsurface manipulations such as those expected from the disposal of heat-emanating radioactive wast...
Finnish spent nuclear fuel is planned to be disposed of deep in the crystalline bedrock of the Olkil...
Finnish spent nuclear fuel final disposal is planned to be based on the Kärnbränslesäkerhet 3-Vertic...
The Swedish Nuclear Fuel and Waste Management Company (SKB) is conducting a series of long term test...
Spent nuclear fuel is planned to be disposed of in deep underground repositories in many countries, ...
In Finland the spent nuclear fuel final repository of Posiva Oy is based on the Swedish KBS-3V multi...
In Finland the spent nuclear fuel final repository of Posiva Oy is based on the Swedish KBS-3V multi...
The Long-Term Test of Buffer Material (LOT) is underway in the Äspö Hard Rock Laboratory in Sweden t...
The Long-Term Test of Buffer Material (LOT) is underway in the Äspö Hard Rock Laboratory in Sweden t...
The Long-Term Test of Buffer Material (LOT) is underway in the Äspö Hard Rock Laboratory in Sweden t...
The effect of exposure to repository-like conditions on compacted Wyoming bentonite was determined b...
The effect of exposure to repository-like conditions on compacted Wyoming bentonite was determined b...
The Long-Term Test of Buffer Material (LOT) is underway in the Äspö Hard Rock Laboratory in Sweden. ...
Compacted bentonite is commonly considered for use as backfill material in emplacement tunnels of nu...
The Long-Term Test of Buffer Material (LOT) is underway in the Äspö Hard Rock Laboratory in Sweden. ...
Subsurface manipulations such as those expected from the disposal of heat-emanating radioactive wast...
Finnish spent nuclear fuel is planned to be disposed of deep in the crystalline bedrock of the Olkil...
Finnish spent nuclear fuel final disposal is planned to be based on the Kärnbränslesäkerhet 3-Vertic...
The Swedish Nuclear Fuel and Waste Management Company (SKB) is conducting a series of long term test...
Spent nuclear fuel is planned to be disposed of in deep underground repositories in many countries, ...
In Finland the spent nuclear fuel final repository of Posiva Oy is based on the Swedish KBS-3V multi...
In Finland the spent nuclear fuel final repository of Posiva Oy is based on the Swedish KBS-3V multi...
The Long-Term Test of Buffer Material (LOT) is underway in the Äspö Hard Rock Laboratory in Sweden t...
The Long-Term Test of Buffer Material (LOT) is underway in the Äspö Hard Rock Laboratory in Sweden t...
The Long-Term Test of Buffer Material (LOT) is underway in the Äspö Hard Rock Laboratory in Sweden t...
The effect of exposure to repository-like conditions on compacted Wyoming bentonite was determined b...
The effect of exposure to repository-like conditions on compacted Wyoming bentonite was determined b...
The Long-Term Test of Buffer Material (LOT) is underway in the Äspö Hard Rock Laboratory in Sweden. ...
Compacted bentonite is commonly considered for use as backfill material in emplacement tunnels of nu...
The Long-Term Test of Buffer Material (LOT) is underway in the Äspö Hard Rock Laboratory in Sweden. ...
Subsurface manipulations such as those expected from the disposal of heat-emanating radioactive wast...