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  • 2015:10 SafePhase: Safety culture challenges in design, construction, installation and commissioning phases of large nuclear power projects

    Different lifecycle phases of a nuclear power plant present new human-technology- organization challenges to regulators and licensees. Organizational processes and practices that have evolved in one phase of development might be dysfunctional for the next phase, and the definition of “good safety culture” in practice might be unclear. The objective of the SafePhase study is to improve the...

    Innehållstyp: Publikationer
  • 2015:12 Interkristallin spänningskorrosion i rostfritt stål i BWR-miljö

    Interkristallin spänningskorrosion (IGSCC) har varit ett problem för kokvattenreaktorer (BWR) sedan 1960-talet, då sprickor påträffades i komponenter av sensibiliserat austenitiskt rostfritt stål. Det var dock först under tidigt 1970-tal, i samband med att omfattande interkristallin sprickning upptäcktes i den värmepåverkade zonen (HAZ) invid svetsar...

    Innehållstyp: Publikationer
  • 2015:03 Brottmekaniska K-lösningar för sprickor i massiv stång med icke-linjärt rotationssymmetriskt spänningstillstånd

    Nya K-lösningar är framtagna för 0,0 ≤ a/R ≤ 1,0 och 0,0 ≤ a/b ≤ 1,0 där a är sprickdjupet, b är spricklängdsparameter och R är stångens radie. Lösningarna inkluderar utöver global membranlast och böjlast även rotationssymmetriska spänningsfält upp till och med femte ordningen. Anpassning av ett andragradspolynom utmed...

    Innehållstyp: Publikationer
  • 2014:18 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 2, 3 and 4

    The analytical tools, which are fuel rod computer codes, that Quantum Technologies AB use and develop, contain models of several of the phenomena that are acting on the nuclear fuel (cladding temperature, fission gas driven pressure, strain and stress in the cladding, rod rupture, etc.) and how the separate effects interact in the complex integrated manner. The codes are under constant...

    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 procedure for mechanical testing and statistical analysis of fracture toughness of ferritic steels in the...

    Innehållstyp: Publikationer
  • 2015:20 The effects of mild, acute hypoxia on cognitive performance

    Room air with reduced oxygen levels that prevent materials to ignite and combust is a cost-effective and increasingly popular fire prevention method. For system safety reasons, the effects of hypoxia, that is, the lack of sufficient oxygen (that is, less than 21% oxygen which is the approximate oxygen level of normal air), on cognitive performance of persons working under such conditions are...

    Innehållstyp: Publikationer
  • 2018:26 Reaktorinneslutningarnas respons vid höga inre tryck och reducerad förspänning

    I föreliggande studie har det genom numerisk modellering undersökts huruvida tillämpning av alternativ B enligt Regulatory Guide 1.90 (R.G. 1.90) är ett tillförlitligt sätt att bedöma reaktorinneslutningens integritet. Vid genomförandet har två olika numeriska modeller använts, en global 3D-modell respektive en ringmodell. Resultaten pekar på...

    Innehållstyp: Publikationer
  • 2018:24 Structural equation modelling for analysis of human and organizational factors in nuclear power plant control rooms

    SSM perspective Background During the supervisory work of the Swedish Radiation Safety Authority (SSM), a need was identified to develop the methods used when evaluating control room work in the central control rooms of nuclear power plants. Benchmarking is commonly used today, with reference values from earlier Integrated System Validation (ISV), when ISV is available. Often, ISV performs...

    Innehållstyp: Publikationer
  • 2010:16 Guidance to Risk-Informed Evaluation of Technical Specifications using PSA

    No guidance documents for risk-informed analysis and assessment of changes in Limiting Conditions for Operation (LCO:s) in TS (Technical Specifications) have been available in the Nordic countries. In the U.S. several guidance documents, primarily developed by the owners groups for PWRs and BWRs, exist. Guidance for analysis of TS changes in this report generally follows the U.S. Regulatory...

    Innehållstyp: Publikationer
  • 2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3

    In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive substances. Both qualitative and quantitative measures of the relative risk are allowed to be used. So far only the PWRs in Sweden are using a quantitative procedure to evaluate the risk...

    Innehållstyp: Publikationer