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Din avgränsning ger 326 träffar.

• 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

• 2013:04 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 18

  The program executed in Stage 18 consists of the following three parts: Application of CoreSim with a two-dimensional model of vibrating fuel assemblies, for the calculation of ex-core detector noise throughout a fuel cycle; An investigation of the neutron noise, induced by propagating perturbations, in various thermal and fast reactor systems, in two-group theory; A consistent derivation of...

  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

• 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

• 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

• 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

• 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

• 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

• 2008:07 Modelling of long term geochemical evolution and study of mechanical perturbation of bentonite buffer of a KBS-3 repository

  PART I: The Swedish Nuclear Fuel and Waste Management Co. (SKB) has recently completed a safety assessment project named SR-Can, related to the KBS-3 disposal concept. In this concept, the waste packages are surrounded by a buffer made of either MX-80 or Deponit CA-N bentonite. Interactions between the buffer and groundwater may modify the buffer composition and thus its containment...

  Innehållstyp: Publikationer