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  • 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...

    Innehållstyp: Publikationer
  • 2014:28 Numerical simulation of ductile crack growth in residual stress fields

    The study has shown on the capability of the cell model in capturing the effects on ductile tearing from limited pre-load levels and a residual stress field. Some of the conclusions are as follows: No distinctive influence on the material fracture toughness is observed from pre-loading (work hardening), both tensile and compressive, at room temperature of 1.5 or 3 % total strain. The cell...

    Innehållstyp: Publikationer
  • 2015:10 SafePhase: Safety culture challenges in design, construction, installation and commissioning phases of large nuclear power projects

    Different lifecycle phases of a nuclear power plant present new human-technology- organization challenges to regulators and licensees. Organizational processes and practices that have evolved in one phase of development might be dysfunctional for the next phase, and the definition of “good safety culture” in practice might be unclear. The objective of the SafePhase study is to improve the...

    Innehållstyp: Publikationer
  • 2015:03 Brottmekaniska K-lösningar för sprickor i massiv stång med icke-linjärt rotationssymmetriskt spänningstillstånd

    Nya K-lösningar är framtagna för 0,0 ≤ a/R ≤ 1,0 och 0,0 ≤ a/b ≤ 1,0 där a är sprickdjupet, b är spricklängdsparameter och R är stångens radie. Lösningarna inkluderar utöver global membranlast och böjlast även rotationssymmetriska spänningsfält upp till och med femte ordningen. Anpassning av ett andragradspolynom utmed...

    Innehållstyp: Publikationer
  • 2014:18 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 2, 3 and 4

    The analytical tools, which are fuel rod computer codes, that Quantum Technologies AB use and develop, contain models of several of the phenomena that are acting on the nuclear fuel (cladding temperature, fission gas driven pressure, strain and stress in the cladding, rod rupture, etc.) and how the separate effects interact in the complex integrated manner. The codes are under constant...

    Innehållstyp: Publikationer
  • 2012:07 Implementation of the Master Curve method in ProSACC

    Cleavage fracture toughness data display normally large amount of statistical scatter in the transition region. The cleavage toughness data in this region is specimen size-dependent, and should be treated statistically rather than deterministically. The Master Curve (MC) methodology is a procedure for mechanical testing and statistical analysis of fracture toughness of ferritic steels in the...

    Innehållstyp: Publikationer
  • 2015:20 The effects of mild, acute hypoxia on cognitive performance

    Room air with reduced oxygen levels that prevent materials to ignite and combust is a cost-effective and increasingly popular fire prevention method. For system safety reasons, the effects of hypoxia, that is, the lack of sufficient oxygen (that is, less than 21% oxygen which is the approximate oxygen level of normal air), on cognitive performance of persons working under such conditions are...

    Innehållstyp: Publikationer
  • 2009:15 Improvement and Validation of Weld Residual Stress Modelling Procedure

    Weld residual stresses have a large influence on the behavior of cracks growing under normal operation loads and on the leakage-flow from a through-wall crack. Accurate prediction of these events is important in order to arrive at proper conclusions when assessing detected flaws, for inspection planning and for assessment of leak-before-break margins. Therefore, it is very important to have...

    Innehållstyp: Publikationer
  • 2010:16 Guidance to Risk-Informed Evaluation of Technical Specifications using PSA

    No guidance documents for risk-informed analysis and assessment of changes in Limiting Conditions for Operation (LCO:s) in TS (Technical Specifications) have been available in the Nordic countries. In the U.S. several guidance documents, primarily developed by the owners groups for PWRs and BWRs, exist. Guidance for analysis of TS changes in this report generally follows the U.S. Regulatory...

    Innehållstyp: Publikationer
  • 2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3

    In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive substances. Both qualitative and quantitative measures of the relative risk are allowed to be used. So far only the PWRs in Sweden are using a quantitative procedure to evaluate the risk...

    Innehållstyp: Publikationer