Din avgränsning ger 597 träffar.
-
2010:33 Lineament interpretation Short review and methodology
Swedish Radiation Safety Authority (SSM). The conclusions and viewpoints presented in the report are those of the author and do not necessarily coincide with those of the SSM. In the characterization of a site ... understand the existent framework of brittle deformation zones in the bedrock. These zones have affect on groundwater transport and the hydrochemistry in the bedrock and the rock mechanical properties. The...
Innehållstyp: Publikationer -
2021:02 On Water Induced Sensitization of Ni (Fe,Cr) alloys towards Stress Corrosion Cracking in LWR Piping from 1st Principles Modelling
SSM perspective Background In Swedish Light Water Reactors (LWR), stress corrosion cracking of reactor components and welds occurs from time to time. As the nuclear power plants are ageing, it is essential ... useful. It can be further developed and used to explain, for example, the effect of hydrogen pick-up on the enrichment of chromium at the alloy grain boundaries in LWR environments, and how Li+ from the...
Innehållstyp: Publikationer -
2005:60 Research and Service Experience with Environmentally-Assisted Cracking in Carbon and Low-Alloy Steels in High-Temperature Water
cracking of carbon and low-alloy steels in high-temperature water are reviewed, with special emphasis on the primary pressure-boundary components of boiling water reactors. The main factors controlling the ... for further research are identified. In spite of the absence of stress corrosion cracking in the field, several unfavourable critical parameter combinations, which can lead to sustained, fast stress corrosion...
Innehållstyp: Publikationer -
2022:14 Weld residual stress and strain measurements on a mock-up with single layer strip cladding common in reactor pressure vessels
SSM perspektiv Bakgrund Reaktortryckkärl tillverkas vanligtvis av låglegerade ferritiska stål som på insidan beläggs med ett eller flera lager av rostfritt stål, så kallad plätering eller på engelska cladding ... Pressurized Thermal Shock Analysis for LTO) och redovisas i SSM2020-5721. Daniel Mångård, Jens Gunnars SSM English SSM perspektiv Bakgrund Reaktortryckkärl tillverkas vanligtvis av låglegerade ferritiska stål som...
Innehållstyp: Publikationer -
2016:39 Recommended residual stress profiles for stainless steel pipe welds
Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to analyze stainless steel pipe welds to obtain good estimations ... distributions. Detailed knowledge of the residual stress field in different types of welds is important since they can have substantial influence on degradation mechanisms such as stress corrosion cracking...
Innehållstyp: Publikationer -
2015:08 Technical Note, Rheological properties of the Bentonite Buffer
the project is to provide review comments on SKB’s postclosure safety analysis, SR-Site, for the proposed repository at Forsmark. This technical note reviews SKB:s reporting of the rheological and geomechanical ... densities. Göran Sällfors, GeoForce AB, Göteborg SSM English Objectives of the project The general objective of the project is to provide review comments on SKB’s postclosure safety analysis, SR-Site, for the...
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 ... have been some of the most important in the field. Consequently, the process is well understood both theoretically and practically. As a result of extensive field and laboratory testing, the average value...
Innehållstyp: Publikationer -
2008:16 Review of SKB:s Safety Assessment SR-Can: Contributions in Support of SKI:s and SSI:s Review by External Consultants
presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management ... in Sweden 2010. In support of this application SKB will present a safety report, SR-Site, on the repository’s long-term safety and radiological consequences. As a preparation for SR-Site, SKB published...
Innehållstyp: Publikationer -
2014:46 Technical Note, QA in SKB’s Groundwater Flow Modelling
provide review comments on SKB’s postclosure safety analysis, SR-Site, for the proposed repository at Forsmark. The specific objective is to get an understanding and an assessment of SKB’s quality assurance ... connection to SR-Site. The reliability of the results of the groundwater flow modelling depends inter alia on the quality assurance, in particular in such a complex modelling work that SKB has performed in connection...
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 ... research results in the field of WRS. The major changes applied in the new weld residual stress modelling procedure are: Improved procedure for heat source calibration based on use of analytical solutions...
Innehållstyp: Publikationer