Filtered generated 296 hits.
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2010:22 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 16
This report constitutes Stage 16 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Results up to Stage 15 were reported in SKI and SSM reports, as listed below and in the Summary. The results have also been published in international journals and have been included in both licentiate- and doctor’s degrees.
Content type: Publications -
2011:04 Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components
During the recent years fatigue analysis procedures for nuclear components have been investigated. The most common method so far has been the American code ASME III. The basis for the current design procedures in ASME III is quite old and has now been evaluated against modern data leading to the proposal of modified design curves. Also the effect of the environment has been the subject of...
Content type: Publications -
2010:45 Evaluation of models for cyclic plastic deformation – A literature study
Analysis of nuclear components subjected to cyclic plastic deformation is normally based on the American standard ASME III. With the focus to improve the modeling of the stress-strain response under non-monotonic loading, several models for the analysis of cyclic plastic deformation have been developed in recent years. However, experience shows that the analysis and evaluation of plastic...
Content type: Publications -
2007:05 Development of an Input Model to MELCOR 1.8.5 for Oskarshamn 3 BWR
200 Lars Nilsson SKI English...
Content type: Publications -
2005:60 Research and Service Experience with Environmentally-Assisted Cracking in Carbon and Low-Alloy Steels in High-Temperature Water
In this report, the most relevant aspects of research and service experience with environmentally assisted cracking of carbon and low-alloy steels in high-temperature water are reviewed, with special emphasis on the primary pressure-boundary components of boiling water reactors. The main factors controlling the susceptibility to environmentally assisted cracking under light water reactor...
Content type: Publications -
2002:04 Qualification of Electrical Components in Nuclear Power Plants. Management of Ageing
The work was finished and reported in Swedish in a limited publication 2000, Ingemansson Rapport H-14061-r-I. As the performed work was regarded to be of more general interest it is published again as a research report by the Swedish Nuclear Power Inspectorate. To be used in the international cooperation in nuclear safety it was also translated into English by the inspectorate, which is this...
Content type: Publications -
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...
Content type: Publications -
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...
Content type: Publications -
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...
Content type: Publications -
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...
Content type: Publications