Publications

2005:55 Application of Master Curve Methodology for Structural Integrity Assessments of Nuclear Components

Iradj Sattari-Far, Kim Wallin SKI English...

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

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...

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Filtered generated 254 hits.

2005:55 Application of Master Curve Methodology for Structural Integrity Assessments of Nuclear Components

2005:61 Review and Assessment of SCC Experiments with RPV Steels in Oskarshamn 2 and 3 (ABB Report SBR 99-020)

2004:16e Statement of the Situation Concerning Safety and Radiation Protection at Swedish Nuclear Plants in 2003

2004:09 Low Temperature (320°C and 340°C) Creep Crack Growth in Low Alloy Reactor Pressure Vessel Steel

2004:33 Assessment of Fuel Rod Failure Thresholds for Reactivity Initiated Accidents

2004:19 Propagation of Ultrasound in Claddings

2004:55 Development of an Input Model to MELCOR 1.8.5 for the Ringhals 3 PWR

2004:53 Studies of Corrosion of Cladding Materials in Simulated BWR-environment Using Impedance Measurements

2004:57 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods

2004:34 Sensitivity Study on Clad Tube Failure under Reactivity Initiated Accidents in Light Water Reactors

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