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  • 2001:23 Interactions of Severe Accident Researchand Regulatory Positions (ISARRP)

    This project, started on April 1, 1999, had the specific objectives of determining whether; (i) the focus of the severe accidents (SA) research is consistent with that of the regulatory authorities, (ii) the results obtained so far by SA research satisfy the regulatory concerns, (iii) the future programs, envisaged will address the potential regulatory needs into next century, and (iv) how...

    Innehållstyp: Publikationer
  • 1997:40 Aging of Electrical Components in Nuclear Power Plants

    The purpose of the study reported in SKl Technical Report 93:39 was to evaluate qualification methods for application to components intended to be installed in the containment of nuclear power plants. The study included application of Arrhenius' criterion for thermal aging as well as methodologies for updating (curve-matching, ongoing qualification). This report reviews the results of...

    Innehållstyp: Publikationer
  • 1997:12 Study of International Published Experiences in Joining Copper and Copper-alloys

    This study has revealed a number of joining processes to be used when manufacturing copper-canisters for the final storage of high level nuclear waste. However, the decision on which material and which joining process to be used has to be based on the design criterions. The welding procedure has to be qualified i.e, it shall be demonstrated whether the procedure is capable of fulfilling...

    Innehållstyp: Publikationer
  • 1996:70 Risks from Nuclear Waste

    The first part of this review discusses the importance of risk. Man seems to have a longing for risks, like a part of the human nature. If risks are missing, they have to be invented, as needed parts in the emotional attraction of sports, amusement parks, traveling, etc.; this is the emotional part of risk. There is also a rational part of risk, in selecting such objects in ordinary life big...

    Innehållstyp: Publikationer
  • 96:51 The Flooding Incident at the Ågesta Pressurized Heavy Water Nuclear Power Plant

    This report is a Master's thesis in Nuclear Reactor Engineering to be submitted to the SKi (Swedish Nuclear Power Inspectorate). The work has been performed at the Division of Nuclear Power Safety, KTH,Stockholm. It is an independent investigation of the consequences of the flooding incident at the Agesta HPWR, in Stockholm, Sweden, which occurred on the 1st of May 1969. The issue was raised...

    Innehållstyp: Publikationer
  • 96:40 Status and Use of PSA in Sweden

    The performance and use of PSA:s in Sweden goes back about two decades. During all of this time, the field of PSA has been developing intensively, both internationally and within Sweden. The latest years have been characterised by an increased use of PSA models and results, and by major extensions of existing PSA models. The aim of this document is to describe PSA in Sweden with respect to...

    Innehållstyp: Publikationer
  • 1995:70 Crack Characterisation for In-service

    During in-service inspection by non destructive testing the reliability is highly dependent on how the equipment is adjusted to the specific object and to the anticipated crack features. The crack feature and morphology vary widely between different cracking mechanisms and between material types, in which the cracks appear. The major objective of this study was to characterise a number of...

    Innehållstyp: Publikationer
  • 1994:15 Aging Degradation of Concrete Structures in Nuclear Power Plants

    This report on the aging-related degradation of concrete structures in nuclear power plants was prepared by Battelle Seattle Research Center for the Swedish Nuclear Power Inspectorate (SKI). The purpose of this report is to provide an understanding of how concrete structures in nuclear power plants degrade over time. This report is based on the studies of concrete aging commissioned by the...

    Innehållstyp: Publikationer
  • 1994:14 Evaluation of acceptance criteriafor data on environmentally assistedcracking in light water reactors

    The assessment of possible sub-critical crack growth through environmentally assisted cracking (EAC) is a commonly encountered problem in safety evaluations of light water reactor components. The numerous factors influencing EAC fall into three main groups (material, medium and loading), but their interactions are highly complex. Field assessments usually rely on the evaluation of...

    Innehållstyp: Publikationer