Din avgränsning ger 233 träffar.

• 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

  Innehållstyp: Publikationer

• 2013:01 Validation of Weld Residual Stress Modeling in the NRC International Round Robin Study

  Weld residual stresses (WRS) 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 on weld residual stresses is important to make proper decisions when cracks in weld joints are detected.

  Innehållstyp: Publikationer

• 2012:70 Process Parameters Affecting Inhomogeneity of Material Microstructure

  There’s been a tremendous change in the number, product types, locations, equipment, and manufacturing capabilities of stainless steel producers from the late 1960’s to present.  This reconfiguration of the global steel industry occurred between the early 1970’s to the mid 1980’s and

  Innehållstyp: Publikationer

• 2012:66 Safety Leadership – the managerial art of balancing production pressure and safety

  A substantial part of the project has been dedicated to investigating and characterizing ‘safety leadership’, set in the context of literature on safety leadership, safety culture and safety management, in order to build a solid theoretical basis. The authors have delved deeply into the

  Innehållstyp: Publikationer

• 2012:50 Fatigue Margins for Austenitic Stainless Steels in ASME Boiler and Pressure Vessel Code – A Literature Study

  Knowledge about the margins against fatigue failure in nuclear piping systems is essential. Therefore, the margins in the ASME Boiler and Pressure Vessel Code (section III) fatigue design procedure for austenitic steels, type 304/316, as applied to real components have been investigated in this

  Innehållstyp: Publikationer

• 2012:07 Implementation of the Master Curve method in ProSACC

  Cleavage fracture toughness data display normally large amount of statistical scatter in the transition region. The cleavage toughness data in this region is specimen size-dependent, and should be treated statistically rather than deterministically. The Master Curve (MC) methodology is a

  Innehållstyp: Publikationer

• 2012:03 The IAEA Integrated Regulatory Review Service Mission to Sweden in February 2012

  The Swedish Government decided on January 22, 2009 to mandate the Swedish Radiation Safety Authority, SSM, to apply for an international review of the Author-ity and its areas of supervision, an ‘IRRS’ (Integrated Regulatory Review Service) carried out by the International Atomic Energy Agency

  Innehållstyp: Publikationer

• 2011:33 Mathematical modelling of ultrasonic testing of components with defects close to a non-planar surface

  The report describes work that has been performed in order to model ultrasonic testing of components that contain a defect close to a non-planar surface. The studies have been performed in both 2D and 3D, and in 2D in both the anti-plane (SH) and the in-plane (P-SV). The results show that the

  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

  Innehållstyp: Publikationer

• 2011:29 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 17

  This report constitutes Stage 17 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Results up to Stage 16 were reported in SKI and SSM reports, as listed below and in the Summary. The results have also been

  Innehållstyp: Publikationer