2022

Filtered generated 5 hits.

• 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