Din avgränsning ger 77 träffar.
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1995:19 Non-destructive Assay of Spent BWR Fuel with High-resolution Gamma-ray Spectroscopy
A method, based on high-resolution gamma-ray spectroscopy, has been developed for verification of burnup, cooling time, power history and, to some extent, the initial enrichment of spent BWR fuel. It is shown that, provided that the power history is known and corrected for, bumup and cooling time can be verified with accuracies within 3% and 60 days, respectively, for cooling times up to about...
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 -
1994:28 ”SKIFTNYCKELN”
Denna uppsats beskriver utvecklingen av en metod för bedömning och analys av kommunikation och samspel i kontrollrum på ett kärnkraftverk. Utifrån en övergripande litteraturgenomgång samt intervjuer med berörd personal vid KSU (Kärnkraft-Säkerhet Utbildning) och Ringhals kärnkraftverk konstruerades ett verktyg anpassat för utvärdering...
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 -
1992:3 Characterization of seismic ground motions for probabilistic safety analyses of nuclear facilities in Sweden. SUMMARY REPORT
In Scandinavia seismic activity is generally low. Only a few incidents have been registered in historic time, which might have damaged an industrial plant of today. The risk of a nuclear accident in Sweden, caused by an earthquake, may thus be considered to be low. The two latest reactors Forsmark 3 and Oskarshamn 3 have been analysed and designed to resist a specified earthquake. For the...
Innehållstyp: Publikationer -
1990:5 Granskning av SKBs FoU-Program 89
SKI:s granskning av FoU-program 89 har resulterat i en granskningspromemoria (SKI Teknisk Rapport 90:5) där SKIs samlade synpunkter redovisas. Här återges en sammanfattning av dessa synpunkter inom olika delområden. SKI vill på grundval av erfarenheterna från den genomförda granskningen framföra vissa synpunkter på presentationen av programmet som kan...
Innehållstyp: Publikationer