Filtered generated 403 hits.
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2010:34 The understanding of the formation of valleys and its implication on site characterization: Moredalen and Pukedalen, south-eastern Sweden
This report concerns a study which was initially conducted for the Swedish Nuclear Power Inspectorate (SKI), which is now merged into the Swedish Radiation Safety Authority (SSM). The conclusions and viewpoints presented in the report are those of the authors and do not necessarily coincide with those of the SSM. In south-eastern Sweden, there are a number of over-deepened narrow valleys,...
Content type: Publications -
2011:11 Handling Interfaces and Time-varying Properties in Radionuclide Transport Models
Quintessa’s QPAC code has been used to investigate the Qeq approach. The conclusions from this simulation study are the following. The basic approach to calculating Qeq values is sound, however, narrow channels could lead to the same release as larger fractures with the same pore velocity, so a channel enhancement factor of √10 should be considered. A spalling zone that increases the area of...
Content type: Publications -
2018:08 Calculated radiological consequences of applying European clearance levels to scrap metal from the decommissioning of Swedish nuclear facilities
Background Many practices involving radioactive substances generate materials with potential or known radioactive contamination. Clearance of materials means a decision that such materials can be released from regulatory control and used or disposed of without restrictions from a radiation protection point of view. According to regulations issued by the SSM, such decisions must be based on...
Content type: Publications -
2007:17 Spent Fuel Dissolution and Source Term Modelling in Safety Assessment
SKI is preparing to review the license applications being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB) for a final repository for the geological disposal of spent nuclear fuel (SFL-2) in the year 2009. As part of its preparation, SKI is conducting a series of technical workshops on key aspects of the Engineered Barrier System (EBS) and spent fuel. This workshop...
Content type: Publications -
2007:12 Development of a constitutive model for the plastic deformation and creep of copper and its use in the estimate of the creep life of the copper canister
The copper-iron canister for disposal of nuclear waste in the Swedish Programme has a design life exceeding 100,000 years. Whilst the operating temperature and operating stress are modest, the very long design life does require that the likely creep performance of the canister should be investigated. Many studies have been carried out by SKB but these have all involved very short duration...
Content type: Publications -
2007:19 An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code
The aim of this applied study has been to describe in a systematic way an appropriate methodological sequence for cost estimation of crucial parameters in decontamination and decommission processes. The work has been limited to older nuclear installations and facilities. Furthermore, it may be envisaged that the process of estimating the parameters of decommissioning is one of the main issues...
Content type: Publications -
2012:33 Technical Note, Review of Groundwater Chemistry in SKB’s Safety Assessment SR-Site
This initial review examined SKB’s characterization of groundwater chemistry at the Forsmark site and its evolution during long time periods under different possible climates in the future. The review considered whether the geochemical data provided by SKB are reasonable and sufficient and whether the methods used by SKB for projecting geochemical conditions into the future are appropriate.
Content type: Publications -
2012:36 Technical Note, Documentation and Traceability of Data in SKB’s Safety Assessment SR-Site: Initial Review Phase
On 16th March 2011SKB applied for a licence to construct and operate a spent nuclear fuel encapsulation facility in Oskarshamn Municipality and a final repository for the encapsulated fuel at Forsmark in Östhammar Municipality. SKB’s SR-Site safety assessment for the spent fuel repository is currently being reviewed by the Swedish Radiation Safety Authority, SSM, and its external experts...
Content type: Publications -
2012:34 Technical Note, Review of FEP Handling in the SR-Site Safety Assessment: Initial Review Phase
On 16th March 2011 the Swedish Nuclear Fuel and Waste Management Company, SKB, submitted applications for licences to construct a spent nuclear fuel encapsulation facility in Oskarshamn and a repository for final disposal of the encapsulated fuel in Forsmark. SKB’s applications are currently being reviewed by the Swedish Radiation Safety Authority, SSM, and the Land and Environmental Court in...
Content type: Publications -
2012:30 Technical Note, Initial review of physical properties and processes of the buffer and backfill. THM and other physical processes
The Swedish Radiation Safety Authority (SSM) reviews the Swedish Nuclear Fuel Company’s (SKB) applications under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of a repository for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain information on specific issues. The...
Content type: Publications