Showing 3317 hits for ””
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00:22 Oxide Properties of Autoclaved Zircaloy Cladding Tubes Investigated by the Photoelectric Polarization Method
A.-C. Nystrand SKI English...
Content type: Publications -
00:05 On the Interaction between Fuel Crud and Water Chemistry in Nuclear Power Plants
Jiaxin Chen SKI English...
Content type: Publications -
02:26 User Guide to UTDefect Version 4
Anders Boström SKI English...
Content type: Publications -
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...
Content type: Publications -
2015:37 Models for axial relocation of fragmented and pulverized fuel pellets in distending fuel rods and its effects on fuel rod heat load
Haverifall med kylmedelsförlust (LOCA) i lättvattenreaktorer kan leda till överhettning av bränslestavar, utvidgning av stavarnas kapslingsrör, samt axiell omflyttning av bränslekutsfragment i de delar av stavarna som expanderat. Bränsleomflyttningen kan koncentrera värmebelastningen till en begränsad del av stavarna och därigenom öka risken...
Content type: Publications -
2014:17 Technical Note, Assessment of radiological effects on non-human biota –Main Review Phase
This report presents a review of SKBs assessment of the long-term radiological effects on plants and animals of a deep geological repository as described in SKB report TR-10-08. The SKB report is one of a number contributing to the overall safety assessment, referred to as SR-Site, for the repository. The conclusion of the SKB report was that the ‘study gives no reason to assume that any of...
Content type: Publications -
2015:53 Ductile tearing – Micromechanical analyses and experimental study
In this report, the project "Ductile Tearing-Micromechanical analyses and experimental study" is presented. In the project, numerical cell modeling has been conducted using the shear modified Gurson model proposed by Nahshon and Hutchinson to evaluate its capability in predicting the effect of residual stresses. Experimental work has also been conducted for material characterization.
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 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...
Content type: Publications -
2016:09 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU – radionuclide transport, dose assessment, and safety analysis methodology
Initial review phase SSM English Initial review phase...
Content type: Publications -
2015:40 Technical Note, Assessment of flow-related transport parameters used in the SR-Site safety case
Joel E. Geier SSM English...
Content type: Publications