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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...
Content type: Publications -
2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3
In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive substances. Both qualitative and quantitative measures of the relative risk are allowed to be used. So far only the PWRs in Sweden are using a quantitative procedure to evaluate the risk...
Content type: Publications -
2014:18 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 2, 3 and 4
The analytical tools, which are fuel rod computer codes, that Quantum Technologies AB use and develop, contain models of several of the phenomena that are acting on the nuclear fuel (cladding temperature, fission gas driven pressure, strain and stress in the cladding, rod rupture, etc.) and how the separate effects interact in the complex integrated manner. The codes are under constant...
Content type: Publications -
2009:27 Analysis Strategy for Fracture Assessment of Defects in Ductile Materials
SSM has supported research for investigating the role of secondary stresses when fracture assessments are performed for cracked structures made of ductile materials. There are evidences that indicate that some secondary stresses, such as weld residual stresses, are not as important as primary stresses for estimating the safety margin against rupture (measured by the J-integral) for the type...
Content type: Publications -
2010:46 Development of the PRO-LOCA Probabilistic Fracture Mechanics Code, MERIT Final Report
The MERIT project has been an internationally financed program with the main purpose of developing probabilistic models for piping failure of nuclear components and to include these models in a probabilistic code named PRO-LOCA. The principal objective of the project has been to develop probabilistic models for piping failure of nuclear components and to include these models in a...
Content type: Publications -
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...
Content type: Publications -
2014:32 Technical Note, Assessment of the derivation and use of distribution coefficients and concentration ratios – Main Review Phase
This report presents a review of the approaches and databases which SKB have used to derive concentration ratios (CRs) and distribution coefficients (Kds) to consider if they are robustly derived and fit for purpose. Credible alternative approaches are also considered. The focus of this review are SKB reports R-10-28 and TR-10-07 which describe the available site specific data and the...
Content type: Publications -
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...
Content type: Publications -
2015:29 Technical Note, Quality Assurance in SKB’s Copper Corrosion Experiments
I Sverige planeras slutförvaring av använt kärnbränsle. Metoden som har utvecklats kallas för KBS-3 och den bygger på tre skyddsbarriärer; kopparkapslar, bentonitlera och det svenska urberget. Det specifika syftet med den här rapporten är att få en förståelse för, och en bedömning av, SKB:s kvalitetssäkring av deras försök...
Content type: Publications -
2014:30 Modelling Approaches to C-14 in Soil-Plant Systems and in Aquatic Environments
Substantial expertise on carbon biogeochemistry already exists in the fields of plant physiology and aquatic ecology and therefore is it beneficial to draw on this to identify the important issues. A paper describing the BIOPROTA C-14 model inter-comparisons, and plans for the forward programme was published in Radiocarbon Journal. Further studies on C-14 (including modelling, model...
Content type: Publications