Filtered generated 401 hits.
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2011:04 Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components
During the recent years fatigue analysis procedures for nuclear components have been investigated. The most common method so far has been the American code ASME III. The basis for the current design procedures in ASME III is quite old and has now been evaluated against modern data leading to the proposal of modified design curves. Also the effect of the environment has been the subject of...
Content type: Publications -
2010:45 Evaluation of models for cyclic plastic deformation – A literature study
Analysis of nuclear components subjected to cyclic plastic deformation is normally based on the American standard ASME III. With the focus to improve the modeling of the stress-strain response under non-monotonic loading, several models for the analysis of cyclic plastic deformation have been developed in recent years. However, experience shows that the analysis and evaluation of plastic...
Content type: Publications -
2009:12 Evaluating safety-critical organizations – emphasis on the nuclear industry
The regulator identified a few years ago a need for a better understanding of and a deeper knowledge on methods for evaluating safety critical organisations. There is a need for solid assessment methods in the process of management of organisational changes as well as in continuously performed assessment of organisations such as nuclear power plants. A considerable body of literature exists...
Content type: Publications -
2014:38 Technical Note, Detailed assessment of radionuclide Kd-values for the geosphere-main review phase
The Swedish Radiation Safety Authority (SSM) is reviewing an application submitted by the Swedish Nuclear Fuel and Waste Management Company (SKB) in 2011 to construct and operate a deep geologic repository for spent nuclear fuel at the Forsmark site in the municipality of Östhammar, Sweden. SKB has presented details of its long-term safety assessment, SR-Site, in a main report (SKB, 2011,...
Content type: Publications -
2013:36 Technical Note, Review and assessment of aspects of the Qeq concept – Main Review Phase
This technical review assignment considers the models and abstractions that Swedish Nuclear Fuel and Waste Management Company (SKB) developed to represent transport of dissolved constituents in the near field at the Forsmark site, in particular the Qeq abstraction for diffusive transport. SKB uses the Qeq parameter to scale concentration gradients in order to estimate dissolved-species fluxes...
Content type: Publications -
2014:33 Technical Note, Reproduction of SKB’s Canister Failure Calculations - What-If and ‘Residual’ Scenario to Illustrate Barrier Functions
The Swedish Nuclear Fuel and Waste Management Company (SKB) included analysis of a range of scenarios in its SR-Site report. SKB grouped these scenarios into two categories—main and residual. The main scenario included a likely scenario (corrosion failure) and a less probable scenario (seismicity-induced shear failure). The residual scenario included two unlikely scenarios—isostatic-load and...
Content type: Publications -
2013:35 Technical Note, Rock Mechanics – Confidence of SKB’s models for predicting the occurrence of a damage zone around the excavations – Main Review Phase
This assignment, performed at Southwest Research Institute, focusses on evaluating SKB’s assessment of potential occurrence of damaged rock zones (also referred to as excavation-damaged zone or EDZ) around underground excavations at the site. This report presents the authors’ evaluation of SKB’s assessment in the specific area based on questions raised by SSM. The evaluation includes...
Content type: Publications -
2014:07 Technical Note, Review of the geological mapping and geophysical measurement techniques for the determination of critical properties around deposition holes -Main Review Phase
This Technical Note reports the findings of a detailed evaluation of the geological and geophysical methods proposed by SKB with respect to their ability, resolution, performance, reliability and robustness to measure the geomechanical parameters critical for determining deposition hole acceptability during repository operation. Addressed are specific questions focusing on the detection of...
Content type: Publications -
2014:05 Technical Note, Assessment of flows to deposition holes – Main Review Phase
SKB’s conceptual model for flow through the fractured rock at Forsmark is based on a division between highly fractured deformation zones (described in terms of deterministic geometry), and the more sparsely fractured rock (described in terms of statistical geometry). The model for the highly fractured deformation zones includes several assumptions that are not strongly supported by data,...
Content type: Publications -
2014:17 Technical Note, Assessment of radiological effects on non-human biota –Main Review Phase
This report presents a review of SKBs assessment of the long-term radiological effects on plants and animals of a deep geological repository as described in SKB report TR-10-08. The SKB report is one of a number contributing to the overall safety assessment, referred to as SR-Site, for the repository. The conclusion of the SKB report was that the ‘study gives no reason to assume that any of...
Content type: Publications