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2009:13e 2009 assessment of radiation safety in the Swedish nuclear power plants
This report has been prepared by order of the Swedish government in accordance with the “Governmental directive for the financial year 2009 regarding the Swedish Radiation Safety Authority”. The Swedish Radiation Safety Authority has through its supervision ensured a comprehensive basis for this overall assessment of radiation safety. The overall conclusion is that the radiation safety,...
Content type: Publications -
2011:29 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 17
This report constitutes Stage 17 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Results up to Stage 16 were reported in SKI and SSM reports, as listed below and in the Summary. The results have also been published in international journals and have been included in both licentiate- and doctor’s degrees.
Content type: Publications -
2011:17 Structural Health Monitoring of Piping in Nuclear Power Plants – A Review of Efficiency of Existing Methods
SSM needs to acquire knowledge about new applied Non-Destructive Engineering (NDE) techniques and their efficiency. One area that is discussed more frequently is Structural Health Monitoring (SHM). SSM needs to investigate the international experiences of SHM from the nuclear industry. SSM also wants to have more information about the capabilities and the limitations of NDE methods The first...
Content type: Publications -
2009:27 Analysis Strategy for Fracture Assessment of Defects in Ductile Materials
SSM has supported research for investigating the role of secondary stresses when fracture assessments are performed for cracked structures made of ductile materials. There are evidences that indicate that some secondary stresses, such as weld residual stresses, are not as important as primary stresses for estimating the safety margin against rupture (measured by the J-integral) for the type...
Content type: Publications -
2010:46 Development of the PRO-LOCA Probabilistic Fracture Mechanics Code, MERIT Final Report
The MERIT project has been an internationally financed program with the main purpose of developing probabilistic models for piping failure of nuclear components and to include these models in a probabilistic code named PRO-LOCA. The principal objective of the project has been to develop probabilistic models for piping failure of nuclear components and to include these models in a...
Content type: Publications -
99:10 Verification and Validation of HumanFactors Issues in Control RoomDesign and Upgrades
Systems, facilities and equipment are periodically updated during a power plant's lifetime. This has human factors implications, especially if the central control room is involved. Human factors work may therefore be required. There is an extensive literature on human factors itself, but not so much on how it is verified and validated. Therefore, HRP and the Swedish Nuclear Power Inspectorate...
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 -
99:08 Human Factors Aspects of Non-Destructive Testing in the Nuclear Power Context
J. Enkvist, A. Edland, O. Svenson SKI English...
Content type: Publications -
01:06 International Conference on Water Chemistry of Nuclear Reactor Systems 8
Mattias Jansson SKI English...
Content type: Publications