Din avgränsning ger 724 träffar.
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2017:19 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures, Phase 2
Background In the design of anchorage equipment in concrete structures the beneficial effects of reinforcement are, in most cases, not considered. The American ASCI 349-06 code opens up for a more detailed analysis where the beneficial impact of reinforcement on anchor capacity can be taken into account. How this analysis can be done is, however, not explicitly described in the code. The...
Innehållstyp: Publikationer -
2007:20 Internationellt samarbete inom OECD/NEA 2006 avseende nukleär kriticitetssäkerhet
Deltagande i internationellt samarbete inom OECD/NEA:s Nuclear Science Committee och dess Working Party on Nuclear Criticality Safety har fortsatt under 2006 med stöd av SKI. Inga stora projekt där jag varit mycket aktiv har pågått. Däremot har jag deltagit i arbetet genom granskning av förslag till slutrapporter, vid bedömning av nya projekt samt i fortsatt...
Innehållstyp: Publikationer -
2009:16 Influence of Hardening Model on Weld Residual Stress Distribution
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 in order to arrive at proper conclusions when assessing detected flaws, for inspection planning and for assessment of leak-before-break margins. Therefore, it is very important to have...
Innehållstyp: Publikationer -
2008:30 A model for fission gas release from mixed oxide nuclear fuel
Nuclear fuel containing mixed oxide (MOX) pellets have been used since the 1960's. MOX fuel pellets are made from a mixture of uranium and plutonium oxide. MOX allows the large quantities of fissile isotopes produced and remaining in spent nuclear fuel from light water reactors to be recycled. Producing MOX fuel can be seen as a method to more efficiently use the natural uranium since...
Innehållstyp: Publikationer -
2009:38 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stages 14 and 15
This report constitutes Stages 14 and 15 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Stage 14 was a full one-year project, whereas Stage 15 consisted of a half-year project. Results up to Stage 13 were reported in SKI reports, as listed below and in the Summary. The results have also been published in...
Innehållstyp: Publikationer -
SSM Report 2008:01 A combined deterministic and probabilistic procedure for safety assessment of components with cracks – Handbook
SSM has supported research work for the further development of a previously developed procedure/handbook (SKI Report 99:49) for assessment of detected cracks and tolerance for defect analysis. During the operative use of the handbook it was identified needs to update the deterministic part of the procedure and to introduce a new probabilistic flaw evaluation procedure. Another identified need...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2012:02 Evaluation of activity build-up experiments
This project aims to understand how the water chemistry affects the activity build-up on surfaces in different systems in Swedish nuclear power plants, which in turn provides information on conditions required to reduce the radiation exposure to power plant staff. The study was done to obtain knowledge about water chemistry conditions preferred to minimize the activity build-up. A number of...
Innehållstyp: Publikationer -
2008:21 Sammanfattande bedömning av strålskyddet vid de kärntekniska anläggningarna i Sverige 2007
I rapporten redovisas SSI:s bedömning av de verksamheter som bedrivits under 2007 vid de svenska kärntekniska anläggningarna. Bedömningen är ett resultat av tillsyn mot anläggningarna under året. Peter Hofvander, Lars Malmqvist, maria Lüning, Svante Ernberg, Helén Wijk, Henrik, Efraimsson, Anki Hägg, Karin Fritioff och Anders Wiebert SSI Svenska...
Innehållstyp: Publikationer -
2008:09 The Generalised Ecosystem Modelling Approach in radiological assessment
An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments,...
Innehållstyp: Publikationer