Publications

Showing 594

• 1995:19 Non-destructive Assay of Spent BWR Fuel with High-resolution Gamma-ray Spectroscopy

  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 ... verified with accuracies within 3% and 60 days, respectively, for cooling times up to about 20 years. For cooling times up to about 50 years the corresponding accuracies are 3% and 1.5 years. It is also shown...

  Content type: Publications

• 1995:70 Crack Characterisation for In-service

  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 ... crack orientation, shape, width, surface roughness and branching. The crack parameters were evaluated from failure analyses reported from the nuclear and non-nuclear industry. In addition, a literature review...

  Content type: Publications

• 1995:15 Determination of the Neutron and Photon Dose Equivalent at Work Places in Nuclear Facilities of Sweden

  power plants consist of a mixture of photons and neutrons of various energies. A detector is usually constructed to respond to one type of radiation only and is usually useful in a limited energy range ... containment building of a reactor, the temperature is well above normal room temperatue (up to 45 C) and the acoustic and electromagnetic noise level may be very high. Such envirorunental conditions could influence...

  Content type: Publications

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

  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 ... points can be set so as to rationalize the overall data assessment. Generalised criteria are developed and justified for the individual test parameters within the three groups of factors influencing EAC. However...

  Content type: Publications

• 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 ... of concrete aging commissioned by the United States Nuclear Regulatory Commission (NRC). Mark J. Do and Alan D. Chockie SKI English This report on the aging-related degradation of concrete structures in...

  Content type: Publications

• 1994:08 The content and environmentalimpact from the waste depositoryin Sillamae

  show the major radiological impact to the population in the Sillamae town is the exposure to radon and its daughter products emanating from the depository. The impact on the Gulf of Finland is limited to ... show the major radiological impact to the population in the Sillamae town is the exposure to radon and its daughter products emanating from the depository. The impact on the Gulf of Finland is limited to...

  Content type: Publications

• 94:02 Safety Evaluation by Living Probabilistic Safety Assessment

  G. Johansson and J. Holmberg SKI English...

  Content type: Publications

• 1993:11 Methods for determination of strontium -90 in food and environmental samples by Cerenkov counting

  of yttrium-90 and counting the Cerenkov radiation in a liquid scintillation counter, is applicable for all kind of samples. Prior to analyses liquid samples are evaporated to dryness and ashed. Environmental ... Environmental and food samples are oven dried and ashed. The ash is dissolved in 1 molar hydrochloric acid and, at pH 1.0-1.2 the yttrium-90 is extracted from the solution with 10% HDEHP. All mono and divalent...

  Content type: Publications

• 93:06 CRACKER A Program Coupling Chemistry and Transport, Version 92-11

  A. Emrén SKI English...

  Content type: Publications

• 1992:3 Characterization of seismic ground motions for probabilistic safety analyses of nuclear facilities in Sweden. SUMMARY REPORT

  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 older reactors no corresponding ... corresponding analyses or designs have been made initially. Their general design is robust.and was considered to provide enough safety with regard to earthquakes of the magnitude reasonably to be taken into account...

  Content type: Publications