Two Shotcrete Lined Tunnels in the United Kingdom
The paper describes two large diameter tunnels recently built in southern England where shotcrete has been used as the primary support. The design methodology is described together with...
The Long Term Interim Storage of Spent AGR Fuel
This paper describes the work undertaken by Scottish Nuclear Ltd. on the proposal to construct a naturally cooled dry store for spent advanced gas cooled reactor fuel at Tornes Power Station,...
Spent Fuel Interim Storage: French Experience with Dry Vaults
This paper explains the main criteria which are applied as well as measures taken to preserve cladding integrity for the foreseen duration of storage. It discusses in detail the double...
The Sellafield Repository Project as Seen by the Public?A Comparison of Research Techniques
To see one's organisation through the eyes of others, to monitor that view and to amend it if necessary, is the primary role of the public relations and public affairs function in an establishment....
The Pursuit of International Science Literacy Through Energy Education: An Interdisciplinary Model for Curriculum Development
Over the past two decades science educators have employed the science, technology, and society (STS) framework for framing curriculum and for prescribing instruction. Ongoing world wide...
Carbon-14: Some Evidence of Migration and Experiments on Immobilisation
Carbon-14 that is produced in nuclear reactors by reactions on C, N and O is one of the most biologically dangerous nuclides that are subject to global dispersion (H-3, 85-Kr, 129-I)....
Role of Fracture Zones in Controlling Hydraulic Head and Groundwater Flow?Experience from Site Characterization Program in Finland
The preliminary site investigations for the final disposal of HLW produced by TVO have been carried out during 1987 - 1992 in five areas. All the areas consist of Precambrian crystalline...
Discrete Feature Modelling at the Stripa Mine in Sweden: Significance for Hydrologic Modelling of Fractured Rock Masses
The third and final phase of the Stripa Project included a series of characterization efforts, predictions, and validations to determine the viability of discrete-fracture groundwater...
Hydrogeochemical Site Investigations by Teollisuuden Voima Oy, Finland
Groundwater samples collected from cored boreholes (500-1000 m), borehole wells and multilevel piezometers in crystalline bedrock have been characterized and classified. The reference...
Organic Carbon Input in Shallow Groundwater at ?SP?, Southeastern Sweden
The variation in carbon and oxygen isotopes in calcite fissure fillings and dissolved carbonate from shallow groundwaters has been examined at Aspo, southeastern Sweden. The shallow water...
Management of Spent Nuclear Fuel in Sweden?Experiences and Plans
The principle adopted for the management of spent nuclear fuel from the Swedish reactors is final disposal without reprocessing. During the 1980ies systems and facilities for the transport...
The Swedish Dialogue Project. An Attempt to Explore How Different Actors May Take Part in the Decision Process Related to Disposal of Radioactive Waste
The Swedish Nuclear Power Inspectorate (SKI) has initiated a project, DIALOGUE, which is exploring the possibility to define review procedures for license applications of nuclear waste...
Scenario Development for Safety Demonstration for Deep Geological Disposal in Switzerland
A scenario development procedure has been developed that is appropriate to the safety assessment approach chosen by Nagra and to the Swiss regulatory requirements. The procedure is seen...
Automatic Calibration of 3D Finite Differences Model Parameters? Application to the Finnsjon Site (Sweden)
Calibration of 3D finite difference model parameters is usually carried out using a noon-automatic 'manual' procedure until observed heads, for instance, are simulated with a sufficient...
Recent Management Experience of UK Performance Assessments of Radioactive Waste Disposal
The approach to management used over the past decade by a UK Government regulatory body (HMIP) to develop, test and apply integrated risk assessment methods, using a team of private contractors,...
Remote Spent Fuel Handling in France at the La Hague Cask Unloading Facility
French policy for the back end of fuel cycle is based on spent fuel reprocessing. Irradiated spent fuels are transferred in casks from the nuclear reactors to the reprocessing plant where...
Evaluation of Spent Fuel Behavior Under Interim Storage Conditions in Russia
The nuclear power in Russia is based on three types of water cooled power reactors VVER-440, -1000 and RBMK-1000. Two fast sodium cooled reactors-prototypes BN-350 and BN-600 are in commercial...
Evaluation of Neutron Emission from Vitrified HLW Compositions
Neutron radiological hazards from vitrified HLW are important for handling and transportation - especially if the concept of separate storage of concentrated transuranics is adopted, as...
Use of Coupled Geochemical and Transport Calculations for Nuclear Waste Problems
The dissolution and migration of radionuclides from a final repository for radioactive waste is complex chemically. The dissolution and release rates depend on the chemistry and on advective...
Groundwater Flow Modelling for the TVO-92 Safety Analysis of Spent Fuel Disposal
The TVO-92 safety analysis of spent fuel disposal is based on preliminary site investigations carried out at five sites in Finland between 1987 and 1992. Groundwater flow analyses have...
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