Filtered generated 373 hits.
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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 -
2012:44 Technical Note, Review of Matrix Diffusion and related properties of intact rock in SKB’s Licence Application for a Spent Nuclear Fuel Repository in Forsmark, Sweden
This report summarizes a review of SKB’s theoretical development of matrix diffusion, its associated processes and parameters, and the data supporting calculations of matrix diffusion. In addition to diffusion, this review covers matrix porosity, the formation factor, matrix diffusivity, penetration depth, and measurement of some of these parameters with electrical methods. Sorption and the...
Content type: Publications -
2012:47 C-14 Long-Term Dose Assessment: Data Review, Scenario Development, and Model Comparison
BIOPROTA (www.bioprota.org) is an international collaboration forum which seeks to provide a transparent and traceable basis for the choices of parameter values, as well as for the wider interpretation of information used in assessments. Particular emphasis is placed on data required for the assessment of long-lived radionuclide migration and accumulation in the biosphere, and the associated...
Content type: Publications -
2012:62 Technical Note, Review of the MARFA Code
As part of SSM’s Initial Review Phase of SKB’s SR-Site safety assessment of the final disposal of spent nuclear fuel at the Forsmark site, Quintessa has been requested by SSM to review SKB’s MARFA code and consider whether the technical arguments and assumptions used for developing the code are sound, appropriate and adequate to support its use in SR-Site. This Technical Note summarises the...
Content type: Publications -
2014:34 Technical Note, Modelling Comparison of Simple Reference Biosphere Models with LDF Models – Main Review Phase
This Technical Note describes the development of simple reference biosphere models as a means of exploring the Landscape Dose Factor (LDF) approach adopted by SKB in the SR-Site safety assessment for the proposed final disposal of spent nuclear fuel at the Forsmark site. The models are developed and described in a systematic manner, based on international guidance reflected in the...
Content type: Publications -
2012:15 Technical Note, A review of the mechanical integrity of the canister
An introductory review of SR-Site has been conducted with respect to the mechanical integrity of the canister. The review is focused on the copper canister and the nodular cast iron insert. Review results show that a number of loads and loading scenarios for the copper canister has not been analysed by SKB. The importance of sufficient creep ductility of the copper material and sufficient...
Content type: Publications -
2012:25 Workshop on Seismology
This report summarizes the issues discussed at the workshop and extracts the essential viewpoints that have been expressed. The report is not to consider as a comprehensive record of all the discussions at the workshop and individual statements made by workshop participants should be regarded as opinions rather than proven facts. This report includes, apart from the workshop synthesis, the...
Content type: Publications -
2012:50 Fatigue Margins for Austenitic Stainless Steels in ASME Boiler and Pressure Vessel Code – A Literature Study
Knowledge about the margins against fatigue failure in nuclear piping systems is essential. Therefore, the margins in the ASME Boiler and Pressure Vessel Code (section III) fatigue design procedure for austenitic steels, type 304/316, as applied to real components have been investigated in this literature study. It is concluded that the current knowledge about the margins in ASME for...
Content type: Publications -
2009:15 Improvement and Validation of Weld Residual Stress Modelling Procedure
Weld residual stresses have a large influence on the behavior of cracks growing under normal operation loads and on the leakage-flow from a through-wall crack. Accurate prediction of these events is important in order to arrive at proper conclusions when assessing detected flaws, for inspection planning and for assessment of leak-before-break margins. Therefore, it is very important to have...
Content type: Publications -
2014:28 Numerical simulation of ductile crack growth in residual stress fields
The study has shown on the capability of the cell model in capturing the effects on ductile tearing from limited pre-load levels and a residual stress field. Some of the conclusions are as follows: No distinctive influence on the material fracture toughness is observed from pre-loading (work hardening), both tensile and compressive, at room temperature of 1.5 or 3 % total strain. The cell...
Content type: Publications