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  • 2020:07 Fibre Clogging in Nuclear Power Plants

    SSM perspective Background Emergency core cooling systems in boiling- and pressurized water reactors use strainers. Their purpose is to out foreign material suspended in the cooling water so this material does not reach the reactor. After the 1992 event at Barsebäck nuclear power plant when the strainers of the emergency cooling system was clogged due to fibers in the cooling water, all...

    Content type: Publications
  • Licensing and notification

    This page contains information about which activities involving radiation require a licence or are subject to a notification obligation. You will also find guidance on how to apply for a licence or notify us about your operations.

    Content type: Regular Pages
  • 2020:12 Assessment of the QT-COOL coolant channel module against the PBF RIA 1-2 experiment

    SSM perspective Background The fuel rod analysis program SCANAIR has been developed by IRSN (Institut de Radioprotection et de Sûreté Nucléaire) for analysis of reactivity initiated accidents (RIA) in light water reactors. The Swedish Radiation Safety Authority (SSM) has access to SCANAIR in exchange for annual contributions for its further development. This ensures a possibility...

    Content type: Publications
  • 2025:01 Safety Concept Evaluation with Failure Tolerance Analysis

    SSM perspective Background One of the most important design principles to achieve high safety function dependability is the use of redundancy to be single-fault tolerant. In turn, redundancies become effective by applying additional design principles such as physical and functional separation and diversity. License holders of nuclear power reactors must demonstrate that requirements are met,...

    Content type: Publications
  • 2017:20 Assessment of inertia effects on transient clad-to-coolant heat transfer and coolant flow under reactivity initiated accidents

    In this report, simple hydrodynamic models are used for studying the effects of coolant inertia on fuel-to-coolant heat transfer and coolant flow under reactivity initiated accidents in light water reactors. The objective is to assess if the inertia effects are important enough to warrant modification of QT-COOL, a coolant channel module for two-phase flow that has recently been implemented as...

    Content type: Publications
  • 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...

    Content type: Publications
  • 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...

    Content type: Publications
  • 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...

    Content type: Publications
  • 2011:16 Modelling of ultrasonic testing of cracks in cladding

    During the last two decades, SSM has supported research to develop a model for the non-destructive test situation based on ultrasonic technique. Such a model is important in many ways, for example to supplement and plan experimental studies and to perform parametric studies in qualification situation. Modeling can be a useful tool when the inspection system shall be technically justified.

    Content type: Publications
  • 2020:13 Core data Research at Uppsala University

    SSM perspective Background This project is to support a research group at Uppsala University in the research field of nuclear data for applications. Nuclear data research is about measuring microscopic cross-sections and developing theoretical nuclear models to create evaluated nuclear data libraries. These nuclear data libraries are used in different applications such as, nuclear technology,...

    Content type: Publications