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  • 2012:70 Process Parameters Affecting Inhomogeneity of Material Microstructure

    There’s been a tremendous change in the number, product types, locations, equipment, and manufacturing capabilities of stainless steel producers from the late 1960’s to present. This reconfiguration of the global steel industry occurred between the early 1970’s to the mid 1980’s and continues today. These changes have produced a loss in manufacturing flexibility, due to the inherent...

    Content type: Publications
  • 2013:27 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures

    The design codes for anchorage of equipment in concrete structures have been developed since the time the Swedish power plants were designed. Furthermore, the design basis has been updated and in some cases new mechanical loads have been added. As a consequence, it can be difficult for some anchorages to meet the requirements of today. In the design of anchorage equipment the beneficial effect...

    Content type: Publications
  • SKI Report 2008:01 Reliability Data for piping Components in Nordic Nuclear Poer Plants "R-Book" Project Phase 1

    SKI Report 2008:01 - “Reliability Data for Piping Components in Nordic Nuclear Power Plants - R-Book Project Phase I” – is a planning document for a new R&D project to develop a piping component reliability parameter handbook for use in probabilistic safety assessment (PSA) and related activities. Included in this handbook will be pipe leak failure rates and rupture frequencies that are...

    Content type: Publications
  • 2008:06 Synthetic Aperture Focusing Technique in Ultrasonic Inspection of Coarse Grained Materials

    Experience from the ultrasonic inspection of nuclear power plants has shown that large focused transducers are relatively effective in suppressing grain (structure) noise. Operation of a large focused transducer can be thought of as an integration (coherent summation) of individual beams reflected from the target and received by individual points at the transducer surface. Synthetic aperture...

    Content type: Publications
  • 2008:50 Study on Developments in Accident Investigation Methods: A Survey of the “State-of-the-Art”

    The objective of this project was to survey the main accident investigation methods that have been developed since the early or mid-1990s. The motivation was the increasing frequency of accidents that defy explanations in simple terms, for instance cause-effect chains or “human error”. Whereas the complexity of socio-technical systems is steadily growing across all industrial domains,...

    Content type: Publications
  • 2007:41 Dependency Analysis Guidence, Nordic/German Working Group on Common cause Failure analysis Phaase 1 project report: Comparison and application to test cases

    The report “Nordic/German Working Group on Common cause Failure analysis. Phase 1 project report: Comparisons and application to test cases” presents a common attempt by the authorities and the utilities to create a methodology and experience base for defence and analysis of dependent failures. The performed benchmark application has shown that how the data is interpreted is of significant...

    Content type: Publications
  • 2016:04 Uncertainty assessment of the SCANAIR V_7_5 computer program in analyses of BWR reactivity initiated accidents

    In this work, we assess uncertainties that can be expected in computational analyses of boiling water reactor reactivity initiated accidents with the SCANAIR V_7_5 computer program. The work is intended to supplement a similar uncertainty assessment, focussed on pressurized water reactor accidents, which is currently being organized as an international benchmark exercise by the OECD Nuclear...

    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 by 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...

    Content type: Publications
  • 2015:50 Assessment of structures subject to concrete pathologies (ASCET)

    Many Nuclear Power Plants around the world are at the moment approaching, or in, their Long Term Operation stage of their operational phase. In addition, several NPPs have recently been carrying out uprate and life extension projects and comprehensive maintenance work including the exchange of components important to safety, in order to extend their lifetime. As a result, ageing management...

    Content type: Publications
  • 2015:38 Evaluation of fatigue in austenitic stainless steel pipe components

    Background Transferability of experimental results obtained for smooth test specimens under constant amplitude loading to realistic components subjected to variable amplitude loading is an important issue in the design against fatigue. There is a lack of experimental fatigue data for austenitic steel components and the present study is an important contribution to fill this gap. Objective The...

    Content type: Publications