Filtered generated 86 hits.
-
2015:30 Technical Note, Rock Mechanics - Assessing the likelihood and extent of fracture growth in the KBS-3 repository at Forsmark
This review work concerns the evaluation of the likelihood and extent of fracture growth around the deposition tunnels and holes of the planned KBS-3 repository at Forsmark. The issues of the isostatic, shear and thermal loading concerning the stability and evolution of rock fractures around the KBS-3 repository at Forsmark are addressed. Hereby, the thermal, glacial and earthquake scenarios...
Content type: Publications -
2015:32 Safe and responsible management of spent nuclear fuel and radioactive waste in Sweden - National Plan
The National Plan describes the general principles (national policies), the legislative, regulatory and organizational framework (national framework) as well as the strategies (national programme and systems) that control the safe and responsible management of spent nuclear fuel and of all types of radioactive waste in Sweden, now and in the future. Flavio Lanaro (project leader), Erica...
Content type: Publications -
2015:52 Technical Note, Review of SKB’s creep model, its implementation into ABAQUS and an evaluation of SKB’s analyses of theevaluation of SKB’s analyses of the copper canister
Peter Segle SSM English...
Content type: Publications -
2013:37 Technical Note, Rock Mechanics – Evolution of fracture transmissivity within different scenarios in SR-Site – Main Review Phase
The current review assignment consists of a literature review and independent modeling for assessing the importance of fracture transmissivity change especially driven by shear loading due to SKB’s thermal, glacial and earthquake loading scenarios for the KBS-3 repository at Forsmark. In the first part of the report, SKB’s laboratory experiments on shear fracture dilation and extensive...
Content type: Publications -
2015:49 Technical Note, Independent Modelling of Engineered Barrier Evolution and Coupled THMC: Canister Corrosion Calculations in SR-Site
Projektets syfte Projektet syftar till att granska olika beräkningsfall för korrosion av kopparkapseln som rapporterats i SKB TR-10-66 och som sammanfattas i SKB TR-11-01. Arbetet omfattar en analys av beräkningsfall relaterade till korrosionshastigheten för intakt buffert, delvis eroderad buffert och för advektiva förhållanden i bufferten. Målsättningen...
Content type: Publications -
2015:10 SafePhase: Safety culture challenges in design, construction, installation and commissioning phases of large nuclear power projects
Different lifecycle phases of a nuclear power plant present new human-technology- organization challenges to regulators and licensees. Organizational processes and practices that have evolved in one phase of development might be dysfunctional for the next phase, and the definition of “good safety culture” in practice might be unclear. The objective of the SafePhase study is to improve the...
Content type: Publications -
2015:09 PROSIR - Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel
Following an OCDE round robin proposal, 16 participants from 9 countries (USA, Japan, Korea (6 participants), Sweden, Germany, Czech Republic, Spain, EC and France (3 participants)) have been involved in a round robin study called PROSIR, Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel. The PROSIR project started already in 2003 and a final draft version of the main report...
Content type: Publications -
2015:04 DiD-PSA: Development of a Framework for Evaluation of the Defence-in-Depth with PSA
The project declares an interpretation of the definitions of Defence in Depth given by IAEA which outline a framework to meet PSA. For each level of defence and combinations of levels, methods to give estimates from a PSA perspective are presented and discussed. One important result is the discussion of the basic definitions and the basis for defence-in-depth, as defined by IAEA, leading to...
Content type: Publications -
2015:50 Assessment of structures subject to concrete pathologies (ASCET)
Many Nuclear Power Plants around the world are at the moment approaching, or in, their Long Term Operation stage of their operational phase. In addition, several NPPs have recently been carrying out uprate and life extension projects and comprehensive maintenance work including the exchange of components important to safety, in order to extend their lifetime. As a result, ageing management...
Content type: Publications -
2015:38 Evaluation of fatigue in austenitic stainless steel pipe components
Background Transferability of experimental results obtained for smooth test specimens under constant amplitude loading to realistic components subjected to variable amplitude loading is an important issue in the design against fatigue. There is a lack of experimental fatigue data for austenitic steel components and the present study is an important contribution to fill this gap. Objective The...
Content type: Publications