Filtered generated 70 hits.
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2011:04 Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components
4640 kB...
Content type: Documents -
2010:36 Guidance for the Definition and Application of Probabilistic Safety Criteria
3981 kB...
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2011:02 The Back-End of the Nuclear Fuel Cycle in Sweden, Considerations for safeguards and data handling
2100 kB...
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2011:29 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 17
863 kB...
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2011:19 Experimental evaluation of influence from residual stresses on crack initiation and ductile crack growth at high primary loads
1516 kB...
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2011:17 Structural Health Monitoring of Piping in Nuclear Power Plants – A Review of Efficiency of Existing Methods
2046 kB...
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2011:16 Modelling of ultrasonic testing of cracks in cladding
994 kB...
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2011:13 Investigation of Discrete-Fracture Network Conceptual Model Uncertainty at Forsmark
3825 kB...
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2011:12 Analysis of Barrier Performance: Modelling of Copper corrosion scenarios with and without buffer erosion
The purpose of this project was to develop a numerical modelling capacity to address the corrosion of the copper canister under gradually changing transport conditions caused by buffer erosion and removal of buffer mass. Due to the complexity of this task, such a model cannot be realistic in all respects, but the present effort should address the feasibility of solving numerical and...
Content type: Publications -
2011:11 Handling Interfaces and Time-varying Properties in Radionuclide Transport Models
Quintessa’s QPAC code has been used to investigate the Qeq approach. The conclusions from this simulation study are the following. The basic approach to calculating Qeq values is sound, however, narrow channels could lead to the same release as larger fractures with the same pore velocity, so a channel enhancement factor of √10 should be considered. A spalling zone that increases the area of...
Content type: Publications