Safety at nuclear power plants

2005:41 Models for Fuel Rod Behaviour at High Burnup

Lars O. Jernkvist, Ali R. Massih SKI English...

Content type: Publications

2005:63 Safety-Related Contractor Activities at Nuclear Power Plants - New Challenges for Regulatory Oversight

Alan Chockie 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

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

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

Content type: Publications

2005:36 Reports within the Area of Nuclear Power Plant Instrumentation

Bengt-Göran Bergdahl SKI English...

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 136 hits.

2005:41 Models for Fuel Rod Behaviour at High Burnup

2005:63 Safety-Related Contractor Activities at Nuclear Power Plants - New Challenges for Regulatory Oversight

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

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

2005:36 Reports within the Area of Nuclear Power Plant Instrumentation

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

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