Safety at nuclear power plants

Filtered generated 14 hits.

• 2005:60 Research and Service Experience with Environmentally-Assisted Cracking in Carbon and Low-Alloy Steels in High-Temperature Water

  In this report, the most relevant aspects of research and service experience with environmentally assisted cracking of carbon and low-alloy steels in high-temperature water are reviewed, with special emphasis on the primary pressure-boundary components of boiling water reactors. The main factors controlling the susceptibility to environmentally assisted cracking under light water reactor...

  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

• 2005:16 Assessment of Core Failure Limits for Light Water Reactor Fuel under Reactivity Initiated Accidents

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

  Content type: Publications

• 2005:41 Models for Fuel Rod Behaviour at High Burnup

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

  Content type: Publications