Din avgränsning ger 724 träffar.
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1997:40 Aging of Electrical Components in Nuclear Power Plants
The purpose of the study reported in SKl Technical Report 93:39 was to evaluate qualification methods for application to components intended to be installed in the containment of nuclear power plants. The study included application of Arrhenius' criterion for thermal aging as well as methodologies for updating (curve-matching, ongoing qualification). This report reviews the results of...
Innehållstyp: Publikationer -
2012:54 Technical Note, Initial Review Phase for SKB´s safety assessment SR-Site: Geological structures and deformation zones, from site investigation to safety assessment
The site selected by the Swedish Nuclear Fuel and Management Co (SKB) for location of a deep geological repository, i.e. a storage for spent nuclear fuel at about 500 m depth in Precambrian metamorphosed rocks. The location of the site is Forsmark at the northern coast of Uppland and 122 km north of Stockholm. In geological terms Forsmark is located in the central part of the Fennoscandian...
Innehållstyp: Publikationer -
2012:58 Technical Note, Independent radionuclide transport modelling – Reproducing results for main scenarios
As part of the initial technical review of SR-Site, we applied a simplified model to approximate Swedish Nuclear Fuel and Waste Management Company (SKB) computations related to the transport of radionuclides at the planned KBS–3 repository at the Forsmark site in Sweden. The objective was to provide insights and recommendations to the Swedish Radiation Safety Authority (SSM) on potential...
Innehållstyp: Publikationer -
2013:34 Technical Note, Seismology – Post-glacial seismicity and paleoseismology at Forsmark
Metoden som SKB använder för att förutse seismisk risk för slutförvaret skiljer sig i två avseenden från gängse förfarande. För det första, förkastningsrörelser inom förvaret är beräknade utifrån numeriska bergmekaniska modeller i stället för genom en Probabilistisk riskanalys för förkastningsrörelse...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2012:47 C-14 Long-Term Dose Assessment: Data Review, Scenario Development, and Model Comparison
BIOPROTA 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 radiological...
Innehållstyp: Publikationer -
2014:10 Technical Note, Rock Mechanics - Confidence of SKB’s models for predicting the occurrence of spalling – Main Review Phase
This review study is placed in the context of SSM’s Main Review Phase for SKB’s safety assessment SR-Site. The assignment is titled “Rock Mechanics – Confidence of SKB’s models for predicting the occurrence of spalling”. The report presents the authors’ assessment in response to the questions raised by SSM. The review concentrated on two main issues: (1) the analysis of the assumptions made...
Innehållstyp: Publikationer -
2014:29 Technical Note, Independent Modelling of Radionuclide Transport, Evaluation of Colloid Transport Modelling – Main Review Phase
SKB excludes consideration of colloids originating inside the canister in its performance assessment on the basis of the filtration capability of the buffer material. In the canister failure by corrosion scenario (central corrosion case), the buffer material is assumed eroded, and the filtration argument is not entirely valid for excluding modelling in-canister colloids. In this Technical...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2010:16 Guidance to Risk-Informed Evaluation of Technical Specifications using PSA
No guidance documents for risk-informed analysis and assessment of changes in Limiting Conditions for Operation (LCO:s) in TS (Technical Specifications) have been available in the Nordic countries. In the U.S. several guidance documents, primarily developed by the owners groups for PWRs and BWRs, exist. Guidance for analysis of TS changes in this report generally follows the U.S. Regulatory...
Innehållstyp: Publikationer