Safety at nuclear power plants

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  • 2023:13 TPR 2023 Fire Protection Swedish National Assessment Report

    Executive Summary The European Union’s Nuclear Safety Directive 2014/87/EURATOM (NSD) requires the member states to undertake topical peer reviews (TPR) every 6 years. The first topical peer review concerned Ageing management and started in 2017. The member states, acting through the European Nuclear Safety Regulators Group (ENSREG), decided that the topic for the second topical peer review...

    Content type: Publications
  • 2022:14 Weld residual stress and strain measurements on a mock-up with single layer strip cladding common in reactor pressure vessels

    Summary Residual stress and strain measurements were performed on a mock-up consisting of a 160 mm thick low-alloy ferritic steel plate of type SA-508 Class 3 with a single layer weld deposited strip cladding of austenitic stainless steel E308L. The cladding was manufactured with submerged arc strip welding adapted to a procedure used for reactor pressure vessels in the 1970s. Comprehensive...

    Content type: Publications
  • 2022:11 Kingdom of Sweden IRRS ARM Summary Report 2022

    The IAEA Integrated Regulatory Review Service Mission to Sweden in November 2022...

    Content type: Publications
  • 2022:09 Assessment of modelling approaches for axial gas flow inside LWR fuel rods

    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. The development...

    Content type: Publications
  • 2022:04 Warm Pre-Stressing mechanisms

    SSM perspective Background Swedish nuclear power plants (NPP) were originally designed and analyzed with an assumed operating period of approximately 40 years. As Swedish NPPs reach their original technical design life the safety of the additional operating time has to be verified. With increased operating time, the shift in the fracture toughness curve of the reactor pressure vessel (RPV)...

    Content type: Publications
  • 2022:03 Effect of Neutron Irradiation on the Oxidation and Corrosion of Austenitic Stainless Steels

    SSM perspective Background Reactor pressure vessel internal components of austenitic stainless steel located close to the core are subject to a high neutron flux. Irradiation by fast neutrons induces changes in the material that affect microstructure, mechanical properties and microchemistry. These changes eventually lead to an increased susceptibility to irradiation assisted stress corrosion...

    Content type: Publications
  • 2021:20 Effects of additives on UO2 fuel behavior: expanded edition

    SSM perspective Background The Swedish Radiation Safety Authority (SSM) follows the development of nuclear fuel closely. Fuel with additives like chromia and gadolinia is used in Swedish reactors and fuel with even better thermal and mechanical properties is under development. This project is an in-depth study of data and models regarding the impact of additives on the properties of uranium...

    Content type: Publications
  • 2021:10 Establishment and use of attention values in environmental fatigue assessments

    SSM perspective Background As Swedish NPPs reach their original technical design life, re-assessment of the fatigue life of structural components is needed for safe long term operation (LTO). In these re-assessments one must consider that new knowledge has shown that environmental effects on fatigue life must be considered. One common method to verify the fatigue life of structural components...

    Content type: Publications
  • 2021:09 Mechanisms important for material modelling in weld residual stress analysis

    SSM perspective Background The prediction of weld residual stresses (WRS) is very complex as many mechanisms and phenomena influence the development of WRS during welding. For accurate prediction, the constitutive material models used are essential and must be able to describe the material response of the weldment constituents. For example, selection of a material model should only depend...

    Content type: Publications