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  • 2021:01 In situ NMR condition monitoring of cable insulations in Nuclear Power Plants

    component installed can function safely in the intended environment. Cables are among the most common components in a nuclear power plant and are required to function during normal operation as well as in the ... the event of an accident. There is a need within the nuclear industry for methodologies which can facilitate on-site measurement for condition monitoring, while having the capability to provide non-destructive...

    Innehållstyp: Publikationer
  • 2007:02e Radiation Environment in Sweden, summary

    The radiation environment to which the population of Sweden is exposed is dominated by medical investigations and background radiation from the ground and building materials in our houses. That is the ... conclusion of the first general Swedish summary of environmental monitoring data and dose calculations within the field of radiation. The report shows that people’s behaviour in the form of their exposure...

    Innehållstyp: Publikationer
  • 2018:15 Review of Geochemical Data Utilisation in SR-Site Safety Assessment

    The Swedish Radiation Safety Authority (SSM) ... reviews and follows associated research related to the Swedish Nuclear Fuel Company’s (SKB) work with establishing a repository for spent nuclear fuel and an encapsulation facility.

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

    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 ... investigation of the neutron noise, induced by propagating perturbations, in various thermal and fast reactor systems, in two-group theory; A consistent derivation of the point kinetic term of the noise in circulating...

    Innehållstyp: Publikationer
  • 1999:13 Determination of the Neutron and Photon Dose Equivalent at Work Places in Nuclear Facilities of Sweden

    mixed neutron-photon fields at workplaccs in the containment of pressurised water reactors and in the vicinity of transport containers with spent fuel elements were investigated with spectrometers and dosimeters ... fluences evaluated from measurements with multisphere systems were recommended to be used for the calculation of dosimetric reference values for comparison with the readings of the dosemeters applied simultaneously...

    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 current report...

    Innehållstyp: Publikationer
  • 1994:14 Evaluation of acceptance criteriafor data on environmentally assistedcracking in light water reactors

    The assessment of possible sub-critical crack growth through environmentally assisted cracking (EAC) is a commonly encountered problem in safety evaluations of light water reactor components. The numerous ... medium and loading), but their interactions are highly complex. Field assessments usually rely on the evaluation of experimental results, with or without parallel attempts to model the cracking process, but...

    Innehållstyp: Publikationer
  • 2012:11 Issues in the corrosion of copper in a Swedish high level nuclear waste repository

    The objective with this research project was to increase knowledge in the area of copper corrosion in the planned repository environment and obtain information on how copper corrosion evolves during the ... the assessment period of 100 000 years.  The equilibrium chemical composition of groundwater close to the canister as a function of temperature has been calculated by use of a thermodynamics code called...

    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, ... Resultaten från mätningarna visade på dragspänningar i nivå med sträckgränsen i pläteringen och cirka 30 mm in i grundmaterialet. Efter värmebehandling konstaterades kraftigt reducerade spänningar i grundmaterialet...

    Innehållstyp: Publikationer
  • 2009:38 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stages 14 and 15

    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 ... 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 international journals and...

    Innehållstyp: Publikationer