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  • 2015:07 TEM-lamella lift-out from the crack tip region of Alloy 600 for high resolution electron microscopy examination

    This report contributes to the development of a method for high-quality TEM lamella preparation from crack tip regions of nuclear materials. A standard compact tension (CT) specimen of Alloy 600 previously tested for stress corrosion crack growth in simulated PWR primary water was used to demonstrate the benefit of the proposed method. This report describes the procedure for cutting the CT...

    Innehållstyp: Publikationer
  • 2015:43 Robust structural verification of pressurized nuclear components subjected to ratcheting

    Background Pressurized components in nuclear applications that are subjected to cyclic loading may exhibit progressive deformation, so called structural ratcheting. If the component is made out of a material that are deformation hardening, it may also exhibit material ratcheting. The combined effects of structural- and material ratcheting are not taken into account in the methods and material...

    Innehållstyp: Publikationer
  • 2014:21 Effects of additives on uranium dioxide fuel behavior

    This report will form a basis for the reviews that SSM does when the license holders applies for use of nuclear fuel with additives. The report is also intended as a reference to the models that Quantum Technologies AB has developed. The report and the models will be a valuable source of information for SSM and other parties when discussing the performance of doped fuel. Ali Massih SSM...

    Innehållstyp: Publikationer
  • 2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents

    Ali R. Massih, Lars Olof Jernkvist SSM English...

    Innehållstyp: Publikationer
  • 2013:25 Anpassning av utbildning till följd av anläggningsförändringar

    Studien baseras på dokumentstudier och intervjuer av personer inom kärnkraftindustrin men även med motsvarande roller inom flyg, petrokemi och massaindustri. De intervjuade har nyckelroller inom simulatorträningen i respektive industri. Inom kärnkraften har personer från ett verk samt från verkens gemensamma utbildningsorganisation intervjuats. De undersökta...

    Innehållstyp: Publikationer
  • 2013:29 Regulatory Approaches in Nuclear Power Supervision

    The objective of this follow-up study was to support SSM in further understanding regulatory approaches and how they can be combined as part of effective strategies. The survey was intended to assist SSM in identifying current standards, experiences, and practices in the regulation of nuclear power plants. The results will also be valuable for the participating authorities as well as other...

    Innehållstyp: Publikationer
  • 2014:13 Förutsättningar för att upprätthålla och utveckla en välfungerande verksamhet kring erfarenhetsåterföring

    Studien har bland annat omfattat att utreda eventuella hinder för tillståndshavarna att upprätthålla och utveckla en effektiv verksamhet kring erfarenhetsåterföring. Studien visade att de största hindren inom de studerade kärnkraftverken ligger i tids- och resursbrist samt i avsaknad av systemstöd och metoder för utvärdering. Processerna förefaller...

    Innehållstyp: Publikationer
  • 2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions

    We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase transformation kinetics, cladding creep deformation, oxidation and rupture as a function of temperature and time in an integrated fashion during the transient. The fuel cladding material...

    Innehållstyp: Publikationer
  • 2014:19 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 5, 6 and 7

    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
  • 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