Filtered generated 763 hits.
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2006:10 Models for MOX fuel behaviour - A selective review
Ali R. Massih SKI English...
Content type: Publications -
00:31 Phenomenological Studies on Melt-Structure-Water Interactions (MSWI) during Severe Accidents
B. R. Sehgal, Z. L. Yang, H. O. Haraldsson, R. R. Nourgaliev, M. Konovalikhin, D. Paladino, A. A. Gubaidullin. G. Kolb, A. Theerthan SKI English...
Content type: Publications -
01:27 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noice Methods
I. Pázsit, C. Demazière, V. Arzhanov, N.S. Garis SKI English...
Content type: Publications -
02:37 Theoretical and Numerical Evaluation of the MTC Noise Estimate in 2-D 2-group Heterogeneous Systems
Christophe Demazière SKI English...
Content type: Publications -
02:55 Experimantal Validation of UTDefect: Scattering in Anisotropic Media and Near-field Behavior
Claudio Pecorari SKI English...
Content type: Publications -
02:48 Evaluation of Results from an In-pile Creep Test in the Studsvik R2 Reactor
Kjell Pettersson SKI English...
Content type: Publications -
01:06 International Conference on Water Chemistry of Nuclear Reactor Systems 8
Mattias Jansson SKI English...
Content type: Publications -
02:27 Guidance for External Events Analysis
Michael Knochenhauer, Pekka Louko SKI English...
Content type: Publications -
2004:16e Statement of the Situation Concerning Safety and Radiation Protection at Swedish Nuclear Plants in 2003
The safety philosophy upon which the Swedish Nuclear Power Inspectorate’s (SKI) supervisory and regulatory activities are based assumes that multiple physical barriers will exist and that a plant-specific defence-in-depth system will be implemented at each plant. The physical barriers are situated between the radioactive material and the plant personnel and surroundings. In the case of...
Content type: Publications -
2005:61 Review and Assessment of SCC Experiments with RPV Steels in Oskarshamn 2 and 3 (ABB Report SBR 99-020)
Although the extent of cracking was rather surprising for a bolt-loaded specimen, the average stress corrosion crack growth rate of 0.5 mm/year over the five-year testing period does not represent an immediate concern. The overwhelming part of crack growth can have occurred during a 20 day chloride transient during the third year of exposure because of a condenser leakage after an outage. The...
Content type: Publications