Reports

Filtered generated 36 hits.

• 2005:42 Phenomenological Studies on Melt-Structure-Water Interactions (MSWI) during Postulated Severe Accidents: Year 2004 Activity

  B.R. Sehgal, H.S. Park, A.K. Nayak, R.C. Hansson, D.Chiferaw, A. Stepanyan, R.S. Rao, A. Karbojian 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

• 2005:51 Hot-Cell Examination of a Defect Rod from IFA-597

  SKI English...

  Content type: Publications

• 2005:64 Investigating conceptual models for physical property couplings in solid solution models of cement

  Steven Benbow, Claire Watson, David Savage SKI English...

  Content type: Publications

• 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

• 2005:07 An Assessment of SKB's Performance Assessment Calculations in the Interim Main Report for the Safety Assessment SR-Can

  Philip Maul, Peter Robinson SKI English...

  Content type: Publications

• 2005:09 Comment on the Long-Term Chemical and Mineralogical Stability of the Buffer

  Randy Arthur, Mick Apted, Mike Stenhouse SKI English...

  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

• 2005:61 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

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

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

  Content type: Publications