Publications

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  • 2016:39 Recommended residual stress profiles for stainless steel pipe welds

    Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to analyze stainless steel pipe welds to obtain good estimations ... since they can have substantial influence on degradation mechanisms such as stress corrosion cracking and fatigue. Residual stresses also have to be considered when assessing safety margins for failure by...

    Content type: Publications
  • 2016:37 PARTRIDGE project: Review and evaluation of the probabilistic fracture mechanics code PRO-LOCA

    Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to evaluate the PRO-LOCA code. It is a computer code, developed ... Battelle in the USA, in which the leak- and rupture probabilities of piping in nuclear power plants are analysed. The pipe systems may contain the damage mechanisms fatigue and/or stress corrosion cracking. In...

    Content type: Publications
  • 2016:28 Fatigue fracture surface characterization and investigation

    examination of the obtained fatigue cracks with the aim of determine where fatigue cracks initiate and how the fatigue cracks propagate in the welded austenitic stainless steel pipes. Results The study ... cracks initiated and how propagation occur in the welded austenitic stainless steel pipes. The main results from the study are: Fatigue cracks were initiated from both the inside and outside of the weld...

    Content type: Publications
  • 2016:27 Validation of fatigue fracture mechanics approaches

    component and the computed fatigue life estimate. Safe and reliable long term operation (LTO) of the plant has to be demonstrated when NPPs approach the end of their design service life time, and this process ... assuming a relatively large initial flaw size and neglecting effects from inelastic material behaviour, sequence effects for variable amplitude loads and crack closure effects. The results support the...

    Content type: Publications
  • 2016:25 Licensing of safety critical software for nuclear reactors

    be limited to verification and testing of the end product, ie the computer code. Other factors such as the quality of the processes and methods for specifying, designing and coding have an important impact ... guidance on the regulatory and safety assessment of these factors. An undesirable consequence of this situation is that the licensing approaches taken by nuclear safety authorities and by technical support organisations...

    Content type: Publications
  • 2016:29 Evaluation of the Swedish participation in the Halden Reactor Project 2006–2014

    2006-2014. The study has consisted in evaluating the types and extent of added value from the Swedish participation in the Halden Reactor Project, and to determine what additional added value the participation ... Reactor Project are extensive and wide ranging, reaching beyond the scope of what has been possible to cover in the evaluation. This limitation is mainly due to the long history and continuity of the collaboration...

    Content type: Publications
  • 2016:31 Measures and method characteristics for early evaluation of safe operation in nuclear power plant control room systems

    construction modifications and other changes. This includes more indepth analysis of the methods used today. Another aspect is that conventional methods of evaluating control rooms and issues need to be reexamined ... evaluation of control rooms. Both the focus and researchers involved have varied over the years. In order to achieve improved research continuity, greater specialisation and a more open approach, SSM decided to...

    Content type: Publications
  • 2016:30 Measurement of Parameter Values for Predicting Corrosion Phenomena on Copper in Swedish HLNW Repositories

    Passivity breakdown and pitting on pure copper, the assumed material for the canisters for the isolation of high-level nuclear waste in Sweden, has been studied in simulated, sulphide- and chloride containing ... granitic rock groundwater and the data are interpreted in terms of the Point Defect Model (PDM). The results indicated that a sulphide barrier layer forms on the copper surface, and that chloride ion can induce...

    Content type: Publications
  • 2016:26 Ensemble for deterministic sampling with positive weights

    which can encode up to four moments and represent any kind of probability distribution, and encode correlations between parameters. This can be used with many parameters, and the number of samples needed scale ... best. DS seems to have potential for uncertainty quantification at SSM, in the nuclear power industry and with heavy calculations done in other field. Arne Sahlberg SSM English The aim of this project is to...

    Content type: Publications
  • 2016:23 Technical Note, Modelling of the thermal evolution of the KBS-3 repository at Forsmark and associated induced seismic activity

    under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of the KBS-3 repository for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions ... commissions consultants to carry out work in order to obtain information and provide expert opinions on specific scientific and technical issues. The results from the consultants’ tasks are reported in SSM’s Technical...

    Content type: Publications