Search

2006:10 Models for MOX fuel behaviour - A selective review

Ali R. Massih 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...

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

Select content type

Select area

Select year

Filtered generated 761 hits.

2006:10 Models for MOX fuel behaviour - A selective review

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

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

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

2005:41 Models for Fuel Rod Behaviour at High Burnup

2004:52 Phenomenological Studies on Melt-Structure-Water Interactions (MSWI) during Postulated Severe Accidents

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

Refine your search

Select content type

Select area

Select year

Monitor via RSS

Search

Select content type

Select area

Select year

Filtered generated 761 hits.

Go to page:

Refine your search

Select content type

Select area

Select year

Monitor via RSS