Din avgränsning ger 738 träffar.
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96:40 Status and Use of PSA in Sweden
The performance and use of PSA:s in Sweden goes back about two decades. During all of this time, the field of PSA has been developing intensively, both internationally and within Sweden. The latest years have been characterised by an increased use of PSA models and results, and by major extensions of existing PSA models. The aim of this document is to describe PSA in Sweden with respect to...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2017:09 Evaluation of the Swedish participation in the Nordic Nuclear Safety Research (NKS) collaboration
Background NKS is a Nordic collaboration promoting cooperation on nuclear safety and emergency preparedness research. The research program is primarily funded by Nordic radiation safety authorities and responsible ministries. The main purpose of NKS is to finance joint Nordic activities and initiatives, including seminars and workshops, technical reports, exercises and scientific articles.
Innehållstyp: Publikationer -
2017:22 Effect of weld repairs on residual stresses in nickel base dissimilar metal welds
Background The driving force for crack growth near welds in nuclear application piping may arise from weld residual stresses. Experience from nondestructive examination show that cracks in dissimilar metal welds are often found near weld repairs. The repair welding may affect the residual stresses through e.g. increased tensile stresses and increased plastic straining on the surfaces of the...
Innehållstyp: Publikationer -
2017:12 Computational assessment of LOCA simulation tests on high burnup fuel rods in Halden and Studsvik
Background Loss of Coolant Accidents (LOCA) are among the most demanding accidents that can happen in a Light Water Reactor (LWR). The lack of cooling and the drop in pressure impose large stresses on the nuclear fuel which would increase the risk of fuel rod damage and the subsequent release of active material. But LOCA is also an accident that the nuclear power plant is designed to...
Innehållstyp: Publikationer -
2017:05 Robust structural verification of pressurized nuclear components subjected to ratcheting, part two – stress-strain curves for cyclic elastoplastic analysis.
Background Pressurized components in nuclear applications that are subjected to cyclic loading may exhibit progressive deformation, so called structural ratcheting. If the component is made out of a material that are deformation hardening, it may also exhibit material ratcheting. The combined effects of structural- and material ratcheting are not taken into account in the methods and material...
Innehållstyp: Publikationer -
2017:32 COMRAD – Comprehensive investigation of the performance of computed and digital radiography
Background Within the industry, there has long been a need to replace the traditional X-ray film and its handling. These both for economic and environmental considerations. Both computed radiography and digital radiography offer many advantages over the traditional use of x-ray with film. However, the transition from film-based radiography requires in-depth knowledge of the relationship...
Innehållstyp: Publikationer -
2018:17 Assessment of structures subject to concrete pathologies (ASCET), phase 2
Background ASCET is an international research project initiated by WGIAGE1 OECD2 / NEA3. WGIAGE4 Concrete subgroup is a working group within the OECD / NEA whose task is to address issues concerning the maintenance of the integrity of concrete structures, proposals for general principles to optimally handle the challenges of integrity, especially with regard to aging of concrete structures.
Innehållstyp: Publikationer -
2010:10 Översikt av nationell och internationell kravbild avseende brandskydd på kärnkraftverk och hur dessa tillämpas i svensk kärnkraftindustri
De nationella föreskrifterna gällande säkerhet på kärnkraftsanläggningar har historiskt behandlat brandskydd på en mycket övergripande nivå och den gällande kravbilden i tillståndshavares SAR, STF, ledningssystem har utvecklats under lång tid men på ett divergerande sätt. Vissa tillståndshavare har valt att följa internationella...
Innehållstyp: Publikationer -
2008:34 Utformning av larmsystem i svenska kärnkraftverk
Det pågår flera stora moderniseringsprojekt inom den svenska kärnkraftindustrin. En del i dessa projekt består av att man helt eller delvis byter ut analoga informations- och manöversystem i kontrollrummen till digitala vilket förändrar larmsystemen. Digitala larmsystem har en mängd fördelar men kan också medföra risker och negativ säkerhetspåverkan.
Innehållstyp: Publikationer