Filtered generated 755 hits.
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02:52 Radiation Shielding Assessment Using the SCALE Computer Code System A demonstration based on an independent review of a real application
Dennis Mennerdahl SKI English...
Content type: Publications -
00:28 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods
I. Pázsit, C. Demazière, S. Avdic, B. Dahl SKI English...
Content type: Publications -
2004:09 Low Temperature (320°C and 340°C) Creep Crack Growth in Low Alloy Reactor Pressure Vessel Steel
Rui Wu, Rolf Sandström, Facredin Seitisleam SKI English...
Content type: Publications -
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 -
2005:51 Hot-Cell Examination of a Defect Rod from IFA-597
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 -
2014:26 Improved reference and relative dosimetry of small radiation therapy photon beams
Data tables on detector corrections for beam output measurements are provided for a large number of detectors (small air and liquid ionization chambers, silicon diodes, TLD and alanine) manufactured by major vendors, for 6 MV photons from clinical accelerators and for two Leksell Gamma Knife® models. They have been calculated with the PENELOPE Monte Carlo system at an uncertainty of 0.1%.
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