Filtered generated 70 hits.
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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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2011:05 Overview and Evaluation of the NESC Projects for Fracture Assessments of Nuclear Components
3134 kB...
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2011:04 Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components
4640 kB...
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2010:36 Guidance for the Definition and Application of Probabilistic Safety Criteria
3981 kB...
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2011:33 Mathematical modelling of ultrasonic testing of components with defects close to a non-planar surface
947 kB...
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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 -
2011:26 The influence of temperature and fluid pressure on the fracture network evolution around deposition holes of a KBS-3V concept at Forsmark, Sweden
In preparation for the review of SKB’s license application for disposal of spent nuclear fuel, SSM is conducting studies to evaluate the performance of the multi-barrier principle on which the KBS-3 concept is based. Copper canisters containing the spent nuclear fuel are placed into granitic bedrock at about 500 m depth and embedded in clay. Thus, the rock, the clay and the copper canister...
Content type: Publications