Filtered generated 758 hits.
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99:08 Human Factors Aspects of Non-Destructive Testing in the Nuclear Power Context
J. Enkvist, A. Edland, O. Svenson SKI English...
Content type: Publications -
99:34 APRI 3 - Accident Phenomena of Risk Importance
SKI English...
Content type: Publications -
98:28 Study of the Possibility of Localising a Channel Instability in Forsmark-1
J. K-H. Karlsson, I. Pázsit SKI English...
Content type: Publications -
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...
Content type: Publications -
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...
Content type: Publications -
97:26 3rd edition Reliability of Piping System Components
Ralph Nyman, Damir Hegedus, Bojan Tomic, Bengt Lydell SKI English...
Content type: Publications -
In case of an alarm from Oskarshamn's nuclear power plant – What you need to know
SSM English...
Content type: Publications -
In case of an alarm from Ringhals nuclear power plant – What you need to know
SSM English...
Content type: Publications -
2020:11 Competency based assessments of Nuclear Power Plant controlroom operators
Experiences of development and first operational methodological and technical demonstrator application...
Content type: Publications -
2020:12 Assessment of the QT-COOL coolant channel module against the PBF RIA 1-2 experiment
SSM perspective Background The fuel rod analysis program SCANAIR has been developed by IRSN (Institut de Radioprotection et de Sûreté Nucléaire) for analysis of reactivity initiated accidents (RIA) in light water reactors. The Swedish Radiation Safety Authority (SSM) has access to SCANAIR in exchange for annual contributions for its further development. This ensures a possibility...
Content type: Publications