Din avgränsning ger 703 träffar.
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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 -
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...
Innehållstyp: Publikationer -
2011:30 A fatigue analysis including environmental effects for a pipe system in a Swedish BWR
The effect of the environment on fatigue design has been the subject of intense study in USA, Japan and elsewhere. Several reports indicate a potentially large influence of the environment, leading to the proposal of entirely new analysis procedures. SSM has in an earlier project sponsored research to evaluate the technical basis for these proposals, see SSM Research Report 2011:04. In the...
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 -
2002:50 Skador i svenska kärnkraftanläggningars mekaniska anordningar 1972-2000
Det är en naturlig del av såväl kraftindustrins verksamhet som Statens kärnkraftinspektions tillsynsuppgift att noggrann följa utvecklingen av inträffade skador. Detta för att kunna vidta åtgärder för att undvika upprepanden och för utveckling av effektiva kontrollprogram. SKI ställer därför krav på erfarenhetsåterföring...
Innehållstyp: Publikationer -
99:35 Beskrivningar och modeller av säkerhetsfunktioner - en förstudie
L. Harms-Ringdahl SKI Svenska...
Innehållstyp: Publikationer -
99:54 Granskningsrapport Ringhals 3 och 4 avseende brandanalys
Ralph Nyman, Peter Jacobsson SKI Svenska...
Innehållstyp: Publikationer -
99:55 Risk Based Test Interval and Maintenance Optimisation Application and Uses
Erik Sparre SKI English...
Innehållstyp: Publikationer -
96:51 The Flooding Incident at the Ågesta Pressurized Heavy Water Nuclear Power Plant
This report is a Master's thesis in Nuclear Reactor Engineering to be submitted to the SKi (Swedish Nuclear Power Inspectorate). The work has been performed at the Division of Nuclear Power Safety, KTH,Stockholm. It is an independent investigation of the consequences of the flooding incident at the Agesta HPWR, in Stockholm, Sweden, which occurred on the 1st of May 1969. The issue was raised...
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